Jy-An John Wang - ORNL



Jy-An John Wang, Ph.D., P.E.

Distinguished R&D Staff

Mechanical Properties and Mechanics Group

Materials Science and Technology Division, Oak Ridge National Laboratory

Phone: (O) 865-574-2274, E-mail: wangja@

Education:

University of California, Berkeley: Division of Structural Mechanics and Materials and Structural Engineering; Major: Mechanics of Materials, Minors: Structural Dynamics and Numerical Analysis; MS.: 1982, Ph.D.: 1987.

National Central University, Taiwan: Major: Structure Mechanics, and Minor: Fluid Mechanics and Dynamics, BS. 1977.

Area of Knowledge and Expertise:

Mechanics and Materials: Solid Mechanics, Fracture Mechanics, Micromechanics, Computational Mechanics, Fluid Mechanics, Composite Materials.

Dynamics: Structural Dynamics, Thermal Dynamics, Random Vibration, Wave Propagation, Soil-Structural Interaction, Fluid Dynamics, High Strain-Rate Testing and Shock Wave Theory.

Material Characterization: Metal and Ceramic Mechanical Testing including tensile, compression, torsion, creep, fatigue, thermal-mechanical fatigue, and fracture toughness testing, Concrete Material Analysis, Ultrasonic Experiment, Ultra-High Compression and X-Ray Diffraction Experiments, Hydrogen Embrittlement, Laser experiment, Stress-Strain Microprobe System, SEM, etc.

Nuclear Science and Radiation Damage: Radiation Damage Mechanism, Radiation Embrittlement Database, Reactor Pressure Vessel (RPV) Surveillance Program, RPV Embrittlement Modeling, Nuclear Data, Dosimetry Method and Neutron Fluence Evaluation, nuclear spent fuel vibration integrity study.

Composite Characterization: Effective Elastic Moduli of Composite Materials, Ice Formation within Composite Materials, Interfacial Characterization of Composite or Functionally gradient Materials.

Structures: Structural Mechanics, Structure Analysis, Steel and RC Structure Design, Metallic and Ceramic Structural Materials, Finite Element Analysis, Boundary Element Method.

Database, etc: Database Development and Management, Applied Regression Method, Experimental Data Fitting Procedures, Numerical Analysis, Neural Networks, Information Fusion.

Professional Experience:

1989 - Present: Oak Ridge National Laboratory, R&D staff, research activities are stated below.

Scope of Research at ORNL:

➢ Material Fatigue and Fracture Toughness Evaluation:

• Invented and developed the cyclic integrated reversible-bending fatigue tester (CIRFT) to investigate spent nuclear fuel vibration integrity.

• Developed protocol for estimating effective lifetime of ACSR connector operating at high temperature; won 2009 R&D 100 Awards.

• Developed cavitation chamber for in-situ cavitation damage study.

• Developed mixed-mode failure testing protocol for Wind turbine blade integrity study.

• Performed low/high cycle fatigue and fracture testing for material performance and lifetime estimate; familiar with high-strain rate material testing and the associated dynamics analysis.

• Performed creep and thermal-mechanical fatigue testing for constitutive model development.

• Investigated the vibration induced fatigue and the associated effective lifetime estimate for pipeline structure, including the associated pump module, for DOT Alaska pipeline vibration project.

• Investigated the reliability and integrity of C7 carbon composite core-aluminum conductor used for high temperature operation in high voltage electric power transmission.

• Developed a table top in-situ cavitation apparatus for investigating the cavitation induced erosion pitting to the pressure boundary.

• Investigated the impact of thermal-mechanical fatigue or aging, induced by thermal cycling, to the integrity of the high voltage powerline connector operated at high temperature.

• Invented and developed the Spiral Notch Torsion Fracture Test (SNTT) System that can be used to determine intrinsic fracture toughness with a miniature specimen. SNTT technology won a 2002 R&D 100 Awards. The strengths of this innovative technique are the ability to carry out miniature testing and mixed-modes evaluation. A mixed-modes failure mechanism can be easily simulated from the proposed specimen configuration and test loading condition. This unique feature can be a great advantage in advanced material research, often only limited material available. But the greatest strength of torsion bar testing is it ability to control crack propagation. With the abilities of confining plastic deformation within a thin plane and controllable crack propagation, it brings up opportunities to investigate and resolve the issues regarding the interfacial material properties, such as heat-affected zone (HAZ) materials and thin-film coating materials.

• SNTT technology minimizes the size effect on fracture toughness evaluation and opens new material research fields in interface fracture toughness study and mixed-mode (Mode I + Mode III) failure research, such as at U-bent top of steam generator tubing. It can also be extended to mixed-mode fracture of high strain-rate loading and to evaluating toughness properties of heat-affected zone (HAZ) of weldments, where the fracture toughness of HAZ material is still a missing link.

• In 2003 received support from ORNL Seed Money Program to carry out a research on “Bi-material interface fracture toughness investigation.” The thin film coating material interface was investigated.

• In 2007 successfully developed new testing protocol for evaluating Mode I fracture toughness of concrete aggregate composite with small specimen.

• Developed apparatus for carrying out in-situ high pressure hydrogen tensile, fracture toughness, and fatigue testing.

• DOE Wind Power Program approved the submitted 2009 proposal on wind turbine blade reliability study related to mixed-mode failure of composite materials.

• NASA approved the submitted jointed proposal with Professor Wayne Chen of Purdue, “Development of An Innovative Technique for Investigating High Strain-Rate, High/Low temperature Mixed-Mode Failure Mechanism.” This proposal was designed to investigate the extreme loading condition of the returning vehicle (space shuttle) and its impact to material behaviors using torsion Hopkinson bar apparatus. Due to the cancellation of NASA JIMO project, the proposed project was not materialized.

➢ Dynamic Response of Structure Materials:

• Worked on wave propagation, structural dynamics, and non-linear finite element modeling.

• Developed a semi-analytical approach that generates an impedance function for seismic loading with a torsional wave form that is associated with soil-structural interaction mechanism.

• Developed dynamics analysis protocol for simulating splice sleeve crimping process used to form high-voltage power line connector.

• Investigated the dynamic impact response of power reactor barrier due to natural disaster, such as tornado missile, or other man-made projectiles.

• Reviewed and completed the update for NRC Standard Review Plan (SRP) 3.5.3, “Barrier Design” on issues related to dynamics impacts.

➢ Material Research, Material Surveillance, and Damage Modeling:

• From 1989 to 1998, Managed and developed the NRC funded “Embrittlement Database (EDB) Program.” The objectives of this program are the following: (1) to construct a well-designed computerized Embrittlement Data Base (EDB), (2) and based on the EDB, develop computational algorithms and analytical program libraries to assess the issues related to radiation damage of reactor pressure vessel (RPV) steels, RPV integrity, and license renewal, (3) acting as a consultant to respond to the technical issues raised by the NRC, utility, and University, related to the integrity of the reactor pressure vessels, and to interact with standard organization to provide the technical bases for voluntary consensus standards that can be used in regulatory guides, standard review plans, and ASME Codes.

• Developed Radiation Embrittlement Database (EDB) for commercial power reactors (PR-EDB) and material test reactors (TR-EDB), which covers the three major categories, namely, RPV material history including chemical compositions and heat treatments, radiation environment, and mechanical test results.

• Developed RPV radiation embrittlement prediction models for US commercial power reactors. Which results in 67.3% and 52.4% reduction in uncertainty of General Electric Boiling Water Reactor’s data compared to that of the current NRC Reg. Guide 1.99, Rev 2’s models, for the base and weld materials, respectively.

• Participated in the developments of ASTM E900 and NRC R.G. 1.99/R3 for RPV embrittlement evaluation.

• Investigated and coordinated the International Atomic Energy Agency development of an IAEA Aging Data Base for reactor pressure vessel and piping systems.

• Investigated the corrosion pitting damage effect on stainless steel 316L of Spallation Neutron Source (SNS) mercury target container due to energetic 1GeV proton pulses.

• Investigated temper embrittlement and hydrogen embrittlement of metallic alloys.

• Investigated steam generator tubing mixed-mode fracture mechanism.

• Investigate the integrity of the advanced nuclear fuel design for space propulsion program.

• Investigated the integrity of the material joining and bi-material interface fracture toughness.

➢ Nuclear Science and Radiation Damage Mechanism:

• Investigated the radiation embrittlement mechanism, including the irradiation temperature effect, neutron fluence rate effect, and chemical composition effect.

• Investigated HFIR accelerated embrittlement due to gamma ray induced displacements. Effects of gamma-induced displacements on HFIR pressure vessel materials was done by carrying out a comprehensive dosimetry experiment, which revealed the presence of an intense gamma field at HFIR. This finding precipitated an assessment of the gamma-induced dpa rate, which was found to exceed the neutron-induced dpa rate at all locations analyzed.

• Investigated the issues related to calculation and dosimetry methods for determining pressure vessel neutron fluence.

• Developed Lead Factor Database for the RPV surveillance program, which contains the evaluated neutron fluence data at surveillance capsules and RPV through wall positions.

• Investigated neutron energy spectrum effect and damage efficiency.

• Investigated the embrittlement of Argentina Atucha-I reactor pressure vessel steel and its related damage mechanisms in Atucha-I heavy water cooled and moderated environment.

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➢ Non-Linear Material Behavior:

• Developed FEM model to simulate the splice connector crimp-forming mechanism and its associated “components contact” problem.

• High voltage power line aluminum conductor materials lifetime estimate at high temperature operation.

• Developed an information fusion technique that bridges the conventional statistical and mechanism model-based approaches into an integrated technology that can predict non-linear material behavior.

• Developed a new Charpy impact data fitting procedure that can properly reflect the characteristic of material inhomogeneity of the reactor pressure vessel (RPV) surveillance materials through a multi-space topography.

• Developed a modified direct method that uses two-phase composite model for determining effective elastic modulus of composite materials.

• Investigated interfacial material properties, such as heat-affected zone of weldment, and interface of the thermal barrier coating materials.

• Investigated the thermal dynamics and heat transfer of bulk amorphous alloy formation.

➢ Computer Code Development:

• Developed TOR3D-KIC computer code to evaluate fracture toughness of 3-D non-coplanar crack front. TOR3D-KIC uses three-dimensional finite element techniques to analyze the crack tip opening displacement (CTOD) occurring on a non-coplanar 3-D spiral crack front. TOR3D-KIC simulates the 3-D spiral crack front and crack propagation orientation during transition phases of fatigue crack growth and the final fracture under pure torsion loading. TOR3D-KIC is used as a means to calculate mode I fracture toughness of metallic and ceramic materials, using a round rod-specimen having a prefabricated spiral V-grooved line with a 45( pitch on the specimen surface.

• Developed a computer code “PT_LIM” for the verification of RPV material degradation during service and determination of operating pressure-temperature (P-T) limits. PT_LIM was developed based on ASME Boiler and Pressure Vessel Code and NRC Standard Review Plan to estimate RPV operating pressure-temperature limits and its related material aging. The details of reactor design and geometry, fuel assembly configuration, and RPV Charpy reference and transition temperatures were registered in P-T database.

• Developed utility programs for database management and data processing.

• Validated and tested ORNL RSICC distributed software and related databases on nuclear science and reactor safety.

➢ In-situ Non-destructive Evaluation:

• Participated in several DOE and DOD SBIR projects related to NDE program development.

• The research subjects focused on innovative in-situ nondestructive testing techniques to characterize material properties, such as automated ball indention technique, deposition energy of shot pinning approach for estimating fatigue damage, and integrated ultrasonic technique utilizing ultrasonic data and two-phase composite models to evaluate damage.

➢ ASTM Standards Development:

• Member of ASTM E10.02 subcommittee, participating in the ASTM semi-annual meetings and the development of many ASTM standards related to integrity of RPV steels, RPV surveillance programs, and fluence evaluation, such as E184, E185, E261, E509, E636, E693, E706, E900, E1214, E1253, E1921, etc.

➢ DHS Advanced Material Council

• Acting as council member in DHS Advanced Material Council since 2009 to assist the advanced material program development for national infrastructure

➢ ASME Pressure Vessel Piping Division Program Development

• Member of ASME Pressure Vessel Piping Division Manufacturing & Fabrication (ASME PVP M-F) Subcommittee, organizing and developing the annual ASME PVP conference and other workshops related to pressure vessel integrity since 2002.

1988-1989 - University of California, Berkeley, Research Engineer.

Worked on interfacial material properties of composites - ultra-high compression technique was used in the study, which included a diamond anvil cell configuration and X-ray diffraction set-up, to estimate the material properties of interfacial material, especially in aggregate composite domain.

1985-1988 - University of California, Berkeley, Research Assistant.

Worked on the subjects of (1) fracture mechanics of composite materials, especially on aggregated composite, (2) ice formation effect in aggregate composites, (3) analytical evaluation of elastic moduli of composite material, (4) utilizing ultrasonic NDE testing procedures and scanning electron microscopy to characterize material properties.

Designed 2 Assembly Buildings based on UBC and California Code with seismic requirement.

1982-1984 - University of California, Berkeley, Research Assistant.

Worked on wave propagation, structural dynamics, and non-linear finite element modeling. Developed a semi-analytical approach for soil-structural interaction study, which generates an impedance function with torsional wave form for seismic dynamic loading.

Technical Papers and Reports:

Refereed Journals

1. Jy-An Wang, “J-integral measured from experimental torque load versus torque-ends rotation angle obtained from a spiral notch torsion test,” Theoretical and Applied Fracture Mechanics 109 (2020) 102721. .

2. Jy-An Wang, “Fracture toughness evaluation for Zr-4 clad tubing structure with pellet inserts,” Theoretical and Applied Fracture Mechanics 108 (2020) 102657.

3. Jy-An Wang, “Fracture toughness evaluation for thin-shell stainless steel weldment,” Theoretical and Applied Fracture Mechanics 106 (2020) 102467. .

4. Jy-An Wang, Ting Tan, “A method for evaluating the fatigue crack growth in spiral notch torsion fracture toughness test,” Archived of Applied Mechanics Journal, (2019) 89:813–822, DOI: 10.1007/s00419-018-1398-2.

5. Hao Jiang, Jy-An Wang, “Development of cone-wedge-ring-expansion test to evaluate the tensile HOOP properties of nuclear fuel cladding,” Journal of Progress in Nuclear Energy, Vol. 108 (2018) 372-380.

6. Jy-An Wang, Hong Wang, Hao Jiang, Bruce Bevard, “High burn-up spent nuclear fuel transport reliability investigation,” Nuclear Engineering and Design Journal, 330 (2018) 497-515, April 2018.

7. Hong Wang and Jy-An John Wang, “Experimental Study on Surrogate Nuclear Fuel Rods Under Reversed Cyclic Bending,” Journal of ASTM International, PP 19-36, STP 1598, 2017, May 2017.

8. Hao Jiang, Jy-An Wang, Hong Wang, “The Impact of Interface Bonding Efficiency on High-Burnup Spent Nuclear Fuel Vibration Integrity,” Journal of Nuclear Engineering and Design, 309 (2016) 40-52.

9. Hao Jiang, Jy-An Wang, “Spent Nuclear Fuel System Dynamic Stability under Normal Conditions of Transport,” Journal of Nuclear Engineering and Design, 310 (2016) 1-14, October 6, 2016.

10. Hong Wang and Jy-An Wang, “Bending testing and characterization of surrogate nuclear fuel rods made of Zircaloy-4 cladding and aluminum oxide pellets,” Journal of Nuclear Materials, 479 (2016) 470-482.

11. Hao Jiang, Jun Qu, Roger Y. Lu, Jy-An John Wang, “Grid-to-rod flow-induced impact study for PWR fuel in reactor,” Progress in Nuclear Energy 91 (2016) 355-361.

12. Jy-An John Wang, Hong Wang, Hao Jiang, Bruce Bevard, "Spent Nuclear Fuel Vibration Integrity Study." WMS Journal, Volume 2, issue 1, October 2016.

13. Jy-An Wang, Hong Wang, Bruce Bevard, Rob Howard, Michelle Flanagan, “Reversal bending fatigue test system for investigating vibration integrity of spent nuclear fuel during transportation,” Journal of Packaging, Transport, Storage & Security of Radioactive Material, Vol. 25 (3-4), p.p. 119-132, 2015.

14. Jy-An Wang, Fei Ren, Ting Tan, Ken Liu, “The development of in situ fracture toughness evaluation techniques in hydrogen environment,” International Journal of Hydrogen Energy, 40 (2015) p.p. 2013-2024, January 2015.

15. Jy-An Wang, Hong Wang, Bruce Bevard, Rob Howard, “New rig for studying SNF vibration integrity,” Journal of Nuclear Engineering International, Vol. 59 (725), p.p. 36-37, December 2014.

16. Hao Jiang and Jy-An Wang, “Methodology for Mechanical Property Testing of Fuel Cladding Using an Expanded Plug Wedge Test,” Journal of Nuclear Materials, vol. 446, pp. 27-37, January 2014.

17. Hong Wang, Jy-An Wang, Ting Tan, Hao Jiang, et al., “Development of U-frame bending system for studying the vibration integrity of spent nuclear fuel,” Journal of Nuclear Materials 440 (2013) 201–213.

18. T. Tan, F. Ren, J-A. Wang, L-C. Edgar, P. Agastra, J. Mandell, W.D. Bertelsen, and C.M. LaFrance, “Investigating fracture behavior of polymer and polymeric composites using the Spiral Notch Torsion Test”, Engineering Fracture Mechanics, Vol. 101, p. 109-128, 2013.

19. F. Ren, J-A. Wang, and B. P. DiPaolo, “Thermomechanical analysis and microstructural characterization of high performance concretes”, J. Mater. Civil. Eng., published online at 10.1061/(ASCE)MT.1943-5533.0000693, 2012.

20. F. Ren, C. H. Mattus, J-A. Wang, and B. P. DiPaolo, “Effect of Projectile Impact and Penetration on the Phase Composition and Microstructure of High-performance Concretes”, Cement and Concrete Composites, Vol. 41, p.1-8, 2013.

21. Hongyu Zhou, Thomas L. Attard, Yanli Wang, Jy-An Wang, and Fei Ren, “Rehabilitation of notch damaged steel beam using a carbon fiber reinforced multiphase-matrix composite”, Composite Structure, published online at

22. F. Ren, J-A. Wang, and W. D. Bertelsen, “Fractographic study of epoxy materials fractured under mode I loading and mixed mode I/III loading”, Materials Science and Engineering A, Vol. 532, p. 449-455, 2012.

23. Jy-An John Wang, Joseph Graziano, John K. Chan, "The Lifetime Estimate for ACSR Single-Stage Splice Connector Operating at Higher Temperatures," IEEE Transactions on Power Delivery, Vol. 26, No. 3, July 2011.

24. F. Ren, J-A. Wang, and H. Wang, “An alternative approach for cavitation damage study using a novel repetitive-pressure-pulse apparatus”, Wear 270[1-2]: 115-119 (2010).

25. Jy-An John Wang, Ken C. Liu, and Dan Naus, "A New Test Method for Determining the Strength and Fracture Toughness of Cement Mortar and Concrete," Concrete & Cement Research, 40 (2010), pp. 497-499, 2010.

26. Jy-An Wang and Ken Liu, "An Innovative Technique for Evaluating Fracture Toughness of Graphite Materials," Journal of Nuclear Materials Vol. 381 (2008) p.177-184.

27. Jy-An John Wang, Ian G. Wright, Michael J. Lance, Ken C. Liu, “A New Approach for Bi-material Interface Fracture Toughness Evaluation,” Journal of Pressure Vessel Technology, Transactions of the ASME, Vol. 130 (2008), 011401-1.

28. Jy-An Wang, Edgar Lara-Curzio, Thomas King, Joe Graziano, John Chan, “The Integrity of ACSR Full Tension Splice Connector at Higher Operation Temperature,” IEEE Transactions on Power Delivery, Vol. 23 (2), pp. 1158-1165, (2008).

29. Jy-An Wang, N.S. Rao, S. Konduri, “The Development of Radiation Embrittlement Models for U. S. Power Reactor Pressure Vessel Steels,” Journal of Nuclear Materials, V. 362 (1), pp. 116-127, 2007.

30. J. A. Wang, N. S. V. Rao, and S. Konduri, “The Information Fusion Embrittlement Models for U.S. Power Reactor Pressure Vessel Steels,” The Effects of Radiation on Materials: ASTM 23rd International Symposium, Journal of ASTM International, 2007.

31. Jy-An John Wang, Ian G. Wright, Michael J. Lance, Ken C. Liu, “A New Approach for Evaluating Thin Film Interface Fracture Toughness,” Material Science and Engineering A, 426 (2006), 332-345.

32. J. A. Wang, Ian G. Wright, Michael J. Lance, Ken C. Liu, “Interface Fracture Toughness Evaluation for MA956 Oxide Film,” Journal of Failure Analysis and Prevention, 5(6), pp. 79-94, December, 2005.

33. J. A. Wang, S. Konduri, N.S. Rao, “Information Fusion Technique For Evaluating Radiation Embrittlement of Reactor Pressure Vessel Steels,” Journal of Pressure Vessel Technology, Vol. 127, pp 98-104, February 2005.

34. J. A. Wang and N. S. Rao, “New Methodologies for Developing Radiation Embrittlement Models and Trend Curves of the Charpy Impact Test Data,” Effects of Radiation on Materials, Vol. 21, pp.634-652, ASTM STP 1447, Journal of ASTM International, December, 2004.

35. J. A. Wang and K. C. Liu, “A New Approach to Evaluate Fracture Toughness of Structural Materials,” Journal of Pressure Vessel Technology, Vol. 126, pp 534-540, November, 2004.

36. Jy-An John Wang, “Oak Ridge National Laboratory Spiral Notch Torsion Test System,” Journal of Practical Failure Analysis, Vol. 3(4) August 2003.

37. J. A. Wang, K. C. Liu, and D. E. McCabe, “An Innovative Technique for Measuring Fracture Toughness of Metallic and Ceramic Materials,” Fatigue and Fracture Mechanics: 33rd Volume, ASTM STP 1417, pp. 757-770, January 2003.

38. J. A. Wang and N. S. Rao, “A New Technique for the Prediction of Nonlinear Material Behavior,” Journal of Nuclear Materials, Vol. 301/2-3, pp. 193-202, March 2002.

39. K. C. Liu and J. A. Wang, “An Energy Method for Predicting Fatigue Life, Crack Orientation, and Crack Growth under Multiaxial Loading Conditions,” International Journal of Fatigue, 23 (2001), S129-S134.

40. J. A. Wang, K. C. Liu, D. E. McCabe, and S. A. David, “Using Torsion Bar Testing to Determine Fracture Toughness, KIC,” Journal of Fatigue & Fracture for Engineering Materials and Structure, Vol. 23, pp 45-56, 2001.

41. J. A. Wang, “Analysis of the Irradiated Data for A302B and A533B Correlation Monitor Materials,” Effects of Radiation on Materials: Vol.19, ASTM STP 1366, pp. 59-80, March 2000.

42. J. A. Wang, “Development of Embrittlement Prediction Models for U.S. Power Reactors and the Impact of the Heat-Affected Zone to Thermal Annealing,” Effects of Radiation on Materials: 18th Volume, ASTM STP 1325, pp. 525-540, March 1999.

43. J. A. Wang, “Using Ultrasonic Measurements and a Two-Phase Composite Model to Assess Radiation Damage in Reactor Pressure Vessel Steels,” Nontraditional Methods of Sensing Stress, Strain, and Damage in Materials and Structures, ASTM STP 1318, pp. 187-197, 1997.

44. F. M. Haggag, J. A. Wang, M. A. Sokolov, and K. L. Murty, “Use of Portable/In-Situ SSM System to Measure Stress-Strain Behavior and Damage in Metallic Materials and Structures,” Nontraditional Methods of Sensing Stress, Strain, and Damage in Materials and Structures, ASTM STP 1318, pp. 85-98, 1997.

45. J. A. Wang, F. B. K. Kam, and F. W. Stallmann, “Embrittlement Data Base (EDB) and Its Applications,” Effects of Radiation on Materials: 17th Volume, ASTM STP 1270, pp. 500-521, August 1996.

46. I. Remec, J. A. Wang and F. B. K. Kam, “HFIR Steels Embrittlement: The Possible Effects of Gamma Field Contribution,” Effects of Radiation on Materials: 17th Volume, ASTM STP 1270, pp. 591-605, August 1996.

47. Remec, I., Wang, J. A., Kam, F. B. K., and Farrell, K., "Effects of Gamma-Induced Displacements on HFIR Pressure Vessel Materials," Journal of Nuclear Material, Volume 217 pp. 258-268, 1994.

48. F. W. Stallmann, F. B. K. Kam, and J. A. Wang, “The Test Reactor Embrittlement Data Base,” Proceedings of the Eighth ASTM-EURATOM Symposium on Reactor Dosimetry, ASTM Special Technical Publication, September 1993.

49. F. B. K. Kam, F. W. Stallmann, and J. A. Wang, “Power Reactor Embrittlement Data Base,” Proceedings of the Seventh ASTM-EURATOM Symposium on Reactor Dosimetry, pp. 41-50, Kluver, Dordrecht /Boston/London, 1990.

50. J. A. Wang, J. Lubliner, and P. J. M. Monteiro, “The Effect of Iceformation on the Elastic Moduli of the Cement Paste and Mortar,” Cement and Concrete Research, Volume 18, pp 874-885, 1988, Pergamon Press, USA.

Refereed Conference Proceedings

1. Viren Thakore, Fei Ren, Hong Wang, Jy-An Wang, Yarom Polsky, High-Temperature Stability of Aqueous Foams as Potential Waterless Hydrofracking Fluid for Geothermal Reservoir Stimulation, Proceedings 45th Workshop on Geothermal Reservoir Engineering, Stanford University, Stanford, California, February 10-12, 2020.

2. Hong Wang, Jy-An Wang, Yarom Polsky, Fei Ren , Viren Thakore, Study of Foam Fracturing for Enhanced Geothermal Systems Using Model Material, Proceedings 45th Workshop on Geothermal Reservoir Engineering, Stanford University, Stanford, California, February 10-12, 2020.

3. Stylianos Chatzidakis, Wei Tang, Jian Chen, Roger Miller, Andrew Payzant, Jeffrey Bunn, Jy-An Wang, Neutron Residual Stress Mapping of Repaired Spent Nuclear Fuel Welded Stainless-Steel Canisters, International High-Level Radioactive Waste Management Conference, April 22, 2019.

4. Hong Wang, Jy-An Wang, Yarom Polsky, Fei Ren, Research Considerations for Foam Fracturing in Stimulation Development for Enhanced Geothermal Systems, Geothermal Reservoir Engineering Workshop Proceedings, 44th Workshop on Geothermal Reservoir Engineering, February 11, 2019.

5. Rose Montgomery, Bruce Bevard, Robert Morris, Benjamin Roach, Zachary Burns, Jy-An Wang, Darren Skitt, Post-irradiation Examinations of High-burnup Pressurized Water Reactor Fuel Rods, EPRI ESCP Meeting, West Palm Beach, FL, May 6, 2019.

6. Stylianos Chatzidakis, Wei Tang, Jian Chen, Roger Miller, Andrew Payzant, Jeffrey Bunn, Jy-An Wang, John Scaglione, Update on Repair Activities at ORNL, Spent Fuel & Waste Disposition Annual Working Group Meeting, Las Vega, Nevada, May 21-23, 2019.

7. Wang, Jy-An, Tan, Ting, “A Method for Evaluating the Fatigue Crack Growth in Spiral Notch Torsion Fracture Toughness,” International Conference on Structural Integrity and Durability 2017, Dubrovnik, Croatia, August 2017.

8. Hong Wang, Jy-An Wang, Hao Jiang, “Fatigue Behavior of Spent Nuclear Fuel Rods in Simulated Transportation Environment,” 2017 ASME PVP Conference, Waikoloa, Hawaii, July 16-20, 2017.

9. Hao Jiang, Jy-An Wang, “Expanding Plug Wedge Test for Evaluating Hoop Tensile Properties of Fuel Cladding,” 2017 ASME PVP Conference, Waikoloa, Hawaii, July 16-20, 2017.

10. Wang, Jy-An, Wang, Hong, Jiang, Hao, “Spent Nuclear Fuel Dynamic Reliability under Normal Condition of Transport with Periodic Transient Shocks,” 14th International Conference on Fracture (ICF 14), Rhodes, Greece, June 2017.

11. Wang, Hong, Wang, Jy-An, et.al., “Structural health monitoring of compression connectors for overhead transmission lines,” Nondestructive Characterization and Monitoring of Advanced Materials, Aerospace, and Civil Infrastructure, SPIE 24th Annual International Symposium on Smart Structures/NDE, 2017 SPIE Volume 10169, May 2017.

12. Wang, Jy-An, “Spent Nuclear Fuel Failure Mechanisms under Normal Condition of Transport”, 2016 EPRI ESCP Meeting, Charlotte, North Carolina, November 2016.

13. Wang, Jy-An John, Hong Wang and Hao Jiang. "Spent Nuclear Fuel Transport Reliability Study." In 2016 PATRAM Conference, Kobe, Japan, September 2016.

14. Wang, Jy-An John, et al. "Spent Nuclear Fuel Dynamic Performance under Normal Condition of Transport." Top Fuel 2016, Boise, Idaho, USA, September 11—16, 2016.

15. Jiang, Hao, Jy-An John Wang and Hong Wang. "Interface Bonding Efficiency Study on High-Burnup Spent Nuclear Fuel." INMM 57th Annual Meeting, Atlanta, Georgia, USA, July 24—28, 2016.

16. Wang, Hong and Jy-An John Wang. "Experimental study on surrogate nuclear fuel rods under reversed cyclic bending." Symposium on Fatigue and Fracture Test Planning, Test Data Acquisition and Analysis, San Antonio, Texas, USA, May 04—05, 2016.

17. Wang, Hong, Wang Jy-An, et.al. "Smart patch integration development of compression connector structural health monitoring in overhead transmission lines." Smart Materials and Nondestructive Evaluation for Energy Systems (SSN10), Las Vegas, Nevada, USA, March 20—24, 2016.

18. Wang, Jy-An John, et al. "Spent Nuclear Fuel Vibration Integrity Study." WM2016 Conference, Phoenix, Arizona, USA, March 06—10, 2016.

19. Jiang, Hao and Jy-An John Wang. "Couple Electrical-Thermal-Structural Joule Heating Simulation of ACSR Splice Connector System." ASME IMECE, Houston, Texas, USA, November 13—19, 2015.

20. Jy-An Wang, Hong Wang, and Hao Jiang, Bruce Bevard, “An Innovative Testing Protocol to Study Spent Nuclear Fuel Vibration Integrity under Normal Condition of Transportation,” 2015 TopFuel Conference, September 13-19, 2015, Zurich, Switzerland.

21. Jy-An Wang, Hong Wang, Hai Jiang, Bruce Bevard, Rob Howard, John Scaglione, “High Burn-Up Spent Nuclear Fuel Vibration Integrity Study,” WM2015 International Conference, Phoenix, AZ, March 15-19, 2015.

22. Jy-An Wang, Hong Wang, Hao Jiang, Bruce Bevard, Rob Howard, John Scaglione, “Lessons Learned From CIRFT Testing on SNF Vibration Integrity Study,” International High-Level Radioactive Waste Management Conference 2015, April 12-16, 2015, Charleston, SC.

23. Hao Jiang, Jy-An Wang, and Hong Wang, “Potential Impact of Interfacial Bonding Efficiency on Used Nuclear Fuel Vibration Integrity during Normal Transportation,” ASME PVP Conference, July 20-24, 2014, Anaheim CA.

24. Hao Jiang, Jy-An Wang, and Hong Wang, “Reversible Bending Fatigue Testing System Design Concepts for Spent Fuel Vibration Integrity Study,” ASME PVP Conference, July 20-24, Anaheim, CA.

25. Jy-An Wang, Hong Wang, Bruce Bevard, Michelle Flanagan, “Surrogate Spent Nuclear Fuel Vibration Integrity Investigation,” 2014 ANS Annual Meeting, June 15-19, 2014, Reno Nevada.

26. Jy-An Wang, Hao Jiang, Hong Wang, “Potential Effect of Interfacial Bonding on Used Nuclear Fuel Vibration Reliability,” 2014 ANS Annual Meeting, June 15-19, 2014, Reno Nevada.

27. Yanli Wang, Yong Lim, Jy-An Wang, et al., “Evaluation of Mechanical Property Testing Procedures and Techniques for Materials in Hydrogen Storage and Transmission,” ASME 2014 8th International Conference on Energy Sustainability, June 30-July 2, 2014, Boston MA.

28. Hao Jiang, Jy-An Wang, et al., “Potential Impact of Interfacial Bonding Efficiency on High-Burnup Spent Nuclear Fuel Vibration Integrity during Normal Transportation,” WM2014 International Conference, Phoenix, AZ, March 02-06, 2014.

29. Jy-An Wang, Hong Wang, Bruce Bevard, “Reversible Bending Fatigue Testing on Zry-4 Surrogate Rods,” Wm2014 International Conference, Phoenix, AZ, March 02-06, 2014.

30. J.-A. Wang, H. Wang, B. Bevard, R. Howard, M. Flanagan, “Reversal Bending Fatigue Test System for Investigating Vibration Integrity of Spent Nuclear Fuel during Transportation,” Proceedings of the 17th International Symposium on the Packaging and Transportation of Radioactive Materials PATRAM 2013, August 18-23, 2013, San Francisco, CA.

31. J.-A. Wang, H. Wang, B. Bevard, R. Howard, M. Flanagan, “Spent Nuclear Fuel Test System for Bending Stiffness and Vibration Integrity,” 2013 International High-Level Radioactive Waste Management Conference, April 28- May 2, 2013, Albuquerque, New Mexico.

32. Jy-An Wang, Ting Tan, and H. Jiang, “Using Spiral Notch Torsion Test to Evaluate Fracture Toughness of Polymeric Composites,” The 19th International Conference on Composite Materials, July 28 – August 2, 2013, Montreal, Canada.

33. F. Ren, Y. Liu, H. Wang, and J-A. Wang, “Development of an erosion/corrosion protocol to evaluate the behavior of casing materials”, 2012 MRS Fall Meeting, Boston, MA, Nov. 25 – 30, 2012.

34. H. Jiang, J-A. Wang, and F. Ren, “Integrity Study of ACSR and ACSS Two Stage Splice Connectors at High Operation Temperatures”, ASME 2012 International Mechanical Engineering Congress & Exposition, Houston, TX, November 9-15, 2012.

35. Jy-An Wang, Ting Tan, and Fei Ren, “Using Spiral Notch Torsion Test to Evaluate Fracture Toughness of Structural Materials and Polymeric Composites,” ACUN6 –Composites and Nanocomposites in Civil, Offshore and Mining Infrastructure Melbourne 14 – 16 November 2012.

36. Wei Zhang, Fei Ren, Zhili Feng, Jy-An Wang, “Design analysis of steel concrete composite vessel for stationary storage of high-pressure hydrogen,” 2012 International Hydrogen Conference, Moran, Wyoming, September 9-12, 2012.

37. W. Zhang, F. Ren, Z. Feng, J. Wang, H. Y. Song, S. S. Babu, M. Boring, L. Hayden, and J. Merrit, “Microstructure of High-Strength Pipeline Steel Welds and their Resistance to Hydrogen Embrittlement”, 9th International Pipeline Conference, Calgary, Alberta Canada, September 24-28, 2012.

38. Jy-An Wang, Fei Ren, Ting Tan, “Spiral Notch Torsion Test Use for Determining Fracture Toughness Of Structural Materials,” 2012 ASME PVP Conference, Toronto, Ontario, Canada, July 15-19, 2012.

39. Sophie Voisin, Fei Ren, Hassina Bilheux, Jy-An Wang, Beverly DiPaolo, “Neutron Imaging of Ultra High Performance Concrete,” American Conference on Neutron Scattering, Washington, DC, June 24-28, 2012.

40. Fei Ren, Jy-An Wang, Yun Liu, Hong Wang, “Development of a Pulsed Pressure-Based Technique for Cavitation Damage Study,” 8th International Symposia on Cavitation, Singapore, August 13-16, 2012.

41. Jy-An Wang, Hao Jiang, Fei Ren, “The Reliability Investigation on ACSR Splice Connector Systems Used in Overhead Power transmission Lines,” International Conference on Renewable Energies and Power Quality, Santiago de Compostela (Spain), March 28-30, 2012.

42. Jy-An Wang, Addis Kidane, “A new Approach to Determine the Quasi-static and Dynamic Fracture Toughness of Materials,” SEM XII International Congress & Exposition on Experimental & Applied Mechanics, Orange County/Costa Mesa, June 11-14, 2012.

43. T. Tan, J-A. Wang, F. Ren, E. Lara-Curzio, P. Agastra, J. Mandell, W. D. Bertelsen, and C. M. LaFrance, “Study of Fracture Behavior of Epoxy and Composite Materials for Wind Turbine Blades Using Spiral Notch Torsion Test”, 2012 Windpower Conferences and Exhibition, Atlanta, GA, June 3 – 6, 2012.

44. Wang, Jy-An John, et al. "Evaluation and improvement of conductor connectors for electrical power transmission system." Materials Challenges in Alternative and Renewable Energy 2012, Clearwater, Florida, USA, February 26 — March 01, 2012.

45. Wang, Jy-An John, et al. "Spiral notch torsion test for fracture behavior evaluation of polymeric composite materials for wind turbine applications." Materials Challenges in Alternative and Renewable Energy 2012, Clearwater, Florida, USA, February 26 — March 01, 2012.

46. J.A. Wang, F. Ren, W. Zhang, Z. Feng, Z. Chen, and H. Xu, “Development of in situ techniques for torsion and tension testing in hydrogen environment”, in Proceedings of the ASME 2011 Pressure Vessels and Piping Conferences, paper no. PVP2011-57676, (2011).

47. W. Zhang, Z. Feng, F. Ren, J-A Wang, and L. Anovitz, “Susceptibility of Carbon Steel Welds to Hydrogen Embrittlement”, FABTECH 2011 - AWS Professional Program, Nov. 13, 2011

48. F. Ren, J. A. Wang, T. Tan, et al. "Fracture study of polymer and polymeric composite materials using the spiral notch torsion test." Materials Science & Technology 2011 Conference & Exhibition, Columbus, Ohio, USA, October 16, 2011.

49. F. Ren, C. Mattus, J. A. Wang, and B. DiPaolo, "Microstructural characterization of UHPC materials subject to impact testing and heating." The 2nd Advances in Cement-based Materials: Characterization, Processing, Modeling and Sensing, Nashville, Tennessee, USA, July 24—26, 2011.

50. Fei Ren, Jy-An Wang, and Bill Bertselsen, "Fracture toughness evaluation of polymeric materials for wind turbine blades using the spiral notch torsion test," Materials Science & Technology 2010 Conference & Exhibition, October 17-21, Houston Texas.

51. Wang, Jy-An John, et al. "Fracture behavior of polymer and polymeric composite materials under mixed mode loading using the spiral notch torsion test." 6th International Conference on Fracture of Polymers, Composites and Adhesives, Les Diablerets, Swaziland, September 11, 2011.

52. Jy-An John Wang, Fei Ren, and Hong Wang, "Cavitation Damage Study Via A Novel Repetitive Pressure Pulse Approach," 2010 ASME PVP Conference, July 18-22, 2010, Bellevue Washington.

53. Ren, Fei, J-A. Wang, et al. "Fracture study of polymer and polymeric composite materials using the spiral notch torsion test." Materials Science & Technology 2011 Conference & Exhibition, Columbus, Ohio, USA, October 16, 2011.

54. Wei Zhang, Zhili Feng, and Jy-An Wang, "Measurement of Fracture Toughness of Materials with Non-uniform Microstructure by Spiral Notch Torsion Test," 2010 ASME PVP Conference, July 18-22, 2010, Bellevue Washington.

55. John Jy-An Wang, Ken C. Liu, and Dan Naus, "A New Test Method for Determining the Strength and Fracture Toughness of Cement Mortar and Concrete," Proceeding of PVP2009, PVP2009-77034, 2009 ASME Pressure Vessels and Piping Conference, Prague, Czech Republic, 2009.

56. John Jy-An Wang, Edgar Lara-Curzio, Tom King, Ke An, and Camden, "Effective lifetime estimate of crimped powerline splice connector operated at high temperature," 2008 ASME PVP Conference, PVP2008-61630, July 27-31, 2008.

57. J.A. Wang, Edgar Lara-Curzio, Thomas King, Joe Graziano, John Chan, “The Integrity of ACSR Full Tension Splice Connector at Higher Operation Temperature,” 2007 IEEE Power Engineering Society General Meeting Conference, pp. 39, Tampa Florida, June 24-28, 2007.

58. J.A. Wang and Ken C. Liu, “An Innovative Small Specimen Technique for Evaluating Fracture Toughness of Structural Materials,” ASTM Fifth Symposium on Small Specimen Test Techniques, January 31-February 1, 2007. 

59. J.A. Wang, Ke An, Edgar Lara-Curzio, Cam Hubbard, Thomas King, Joe Graziano, John Chan "Residual Stress Evaluation within a Crimped Splice Connector Assembly," 2006 Electrical Transmission Conference, pp. 391-404, October 15-19, 2006, Birmingham, Alabama.

60. J.A. Wang, Ke An, Edgar Lara-Curzio, Cam Hubbard, "Residual Stresses/Strains Measurement in a Crimped Splice Connector of High-Temperature Low-Sag Conductors for High-Voltage Transmission Lines," 2006 American Neutron Science Conference.

61. J.A. Wang, “An innovative Fracture Toughness Test for Graphite Materials,” 7th International Nuclear Graphite Specialists Meeting, September 10-13, 2006, Oak Ridge, Tennessee.

62. J. A. Wang, N. S. V. Rao, and S. Konduri, “The Development of Radiation Embrittlement Models For U.S. Power Reactor Pressure Vessel Steels,” Proceedings of PVP2006 2006 ASME Pressure Vessels and Piping Division Conference July 23-27, 2006, Vancouver, BC, Canada.

63. J. A. Wang, Ian G. Wright, Michael J. Lance, Ken C. Liu, “Interface Fracture Toughness Evaluation for MA956 Oxide Film,” Proceeding of 2005 ASM International Surface Engineering Congress, pp 80-89, August 1-3, 2005, St. Paul, Minnesota.

64. Jy-An John Wang, Ian G. Wright, Michael J. Lance, Ken C. Liu, “Determination of Interfacial Fracture Toughness for Thin Film Coating Materials,” 2005 ASME Pressure Vessel Piping Conference, July 17-21, 2005, Denver, Colorado.

65. R. A. Bayles, R. K. Singh Raman, S. P. Knight, J. A. Wang, “Evaluating Stress-Corrosion Cracking Susceptibility Using a Torsion Test,” 2005 ASME Pressure Vessel Piping Conference, July 17-21, 2005, Denver, Colorado.

66. J. A. Wang and N. S. Rao, “Information Fusion Method for Estimating Radiation Embrittlement of Reactor Pressure Vessel Steels,” 13th International Conference on Nuclear Engineering, Beijing, China, May 16-20, 2005.

67. J. A. Wang, K. C. Liu, I. G. Wright, R. L. Xu, “An Innovative Technique For Bi-Material Interface Toughness Research,” IMECE2004, ASME International Mechanical Engineering Congress, November 13–19, 2004, Anaheim, California.

68. Robert Bayles, Steve King, J. A. Wang, “Application of Disc Compact Tension Formulas to Compliance and K-Calibration of Spiral Notch Torsion Test Specimens,” 6th International Aircraft Corrosion Workshop, August 24-27, 2004 at the Holiday Inn Select, Solomons, Maryland.

69. J. A. Wang and N. S. Rao, “A New Approach for Evaluating Radiation Embrittlement of Reactor Pressure Vessel Steels,” Proceedings of ASME Pressure Vessel and Piping, July 2004.

70. R.K. Singh Raman, R. Bayles, S. Knight, Jy-An Wang, B.R.W. Hinton B.C. Muddle, “Development of Spiral Notch Torsion Test (SNTT): A New Fracture Mechanics Approach for Determination of KISCC, Environment-Induced Cracking of Metals Conf., Banff, Canada, 19-23 Sept ’04.

71. J. A. Wang and K. C. Liu, “A New Approach To Evaluate Fracture Toughness of Structural Materials,” Proceedings of ASME Pressure Vessel and Piping, July 2003.

72. J. A. Wang, “A New Methodology for Developing Charpy Impact Data Trend Curves,” Proceedings of 2003 ANS Annual Meeting in Special Session of Reactor Pressure Vessel Embrittlement, June 2003, San Diego California.

73. J. A. Wang and N. S. Rao, “Radiation Embrittlement Prediction Models and the Impact of Irradiation Temperature,” ASTM 11th International Symposium on Reactor Dosimetry, Brussels, August 18-23, 2002.

74. J. A. Wang, Robert C. Singleterry Jr., Ronald J. Ellis, and Hamilton T. Hunter, “Radiation Effects on Spacecraft Structural Materials,” Proceedings of International Conference on Advanced Nuclear Power Plants, June 9-13, 2002, Hollywood, Florida.

75. J. A. Wang, K. C. Liu, and G. A. Joshi, “Using Torsion Bar Testing to Determine Fracture Toughness of Ceramic Materials,” ASME Proceeding of ETCE 2002 Conference on Composite Materials Design & Analysis, February 3-4, 2002, CMDA-29077, Houston, Texas.

76. J. A Wang, J. V. Pace III, and T. M Rosseel, “U.S. NRC Embrittlement Data Base (EDB), ” Reactor Dosimetry, ASTM STP 1398, John G. Williams, David W. Vehar, Frank H. Ruddy, and David Gilliam, Eds., American Society for Testing and Materials, West Conshohocken, pp 657-664, PA, 2000.

77. F. M. Haggag, and J. A. Wang, “Nondestructive Detection and Assessment of Damage in Aging Aircraft Using a Novel Stress-Strain Microprobe System,” Symposium on Nondestructive Evaluation Techniques for Aging Infrastructure & Manufacturing Conference, SPIE vol. 2945, December 1996.

78. J. A. Wang, J. Lubliner, and P. J. M. Monteiro, "The Modified Direct Method for the Calculation of the Elastic Moduli of Composite Materials," Proceedings of the First International Conference on Composites in Infrastructure, Eds. H. Saadatmanesh, and M. R. Ehsani, pp. 80-94, Tucson, Arizona, January 1996.

79. F. B. K. Kam, F. W. Stallmann, and J. A. Wang, “Power Reactor Embrittlement Data Base (PR-EDB): Uses in Evaluating Radiation Embrittlement of Reactor Vessels,” Proceedings of Aging Research Conference, Rockville, Maryland, March 1992.

Technical Reports

1. Hong Wang, Jy-An Wang, Rose Montgomery, Bruce Bevard, CIRFT Data Analysis for Sister Rods, ORNL/TM-2019/1451, August 2020.

2. Jy-An Wang, Fracture Toughness Evaluation for Spent Nuclear Fuel Clad Systems Using Spiral Notch Torsion Fracture Toughness Test, ORNL/TM-2019/1204, June 2019.

3. Jy-An Wang, “Fracture Toughness Evaluation for Sandia Mock-up Stainless Steel Canister Weldment Using Spiral Notch Torsion Fracture Toughness Test,” ORNL/TM-2019/1134, March 2019.

4. Rose Montgomery, Robert Morris, Ralph Ilgner, Jy-An Wang, Zachary Burns, Yong Yan, Riley Cumberland, Benjamin Roach, Sister Rod Destructive Examinations, ORNL/SPR-2019/1112, March 2019.

5. Jy-An Wang, “Development of a Testing Protocol for C7 carbon Fiber Core Conductors,” ORNL /SPR-2018/816, May 2018.

6. Rose Montgomery, Bruce Bevard, Robert N. Morris, Yong Yan, Jy-An Wang, Zachary Burns, Charles Baldwin, “Sister Rod Destructive Examination Status Report,” ORNL/SPR-2018/957, September 2018.

7. Jy-An Wang, Andrew Payzant, Jeff Bunn, Ke An, “Neutron Residual Stress Mapping for Spent Nuclear Fuel Storage Canister Weldment,” ORNL/TM-2018/827, April, 2018.

8. Jy-An Wang, Hong Wang, “FY 2017 Status Report: CIRFT Data Update and Data Analyses for Spent Nuclear Fuel Vibration Reliability Study,” ORNL/SPR-2017/521, SFWD-SFWST-2017-000030/R1, November 2017.

9. Jy-An Wang, Hong Wang, “Mechanical Fatigue Testing of High Burnup Fuel for Transportation Applications,” NUREG/CR-7198/R1, June 2017.

10. Jy-An Wang, Hong Wang, “FY 2017 Status Report: CIRFT Data Update and Data Analyses for Spent Nuclear Fuel Vibration Reliability Study,” ORNL/SR-2017/291, M3SF-17OR010201026, SFWD-SFWST-2017-000030, August 2017.

11. Wang, Jy-An, Jiang, Hao, “Sag Study of Overhead Transmission Conductors ACSR and ACSS under Tension and High Temperature,” ORNL/LTR-2017/20, January 2017.

12. Wang, Jy-An, Jiang, Hao, “Development of Cone Wedge Ring Expansion Test to Evaluate Mechanical Properties of Clad Tubing Structure,” ORNL/TM-2016/279, October 2016.

13. Wang, Jy-An, Wang, Hon, “ORNL Interim Progress Report on Static CIRFT Testing Curvature Data Update,” ORNL/TM-2016/619, October 2016.

14. Wang, Jy-An, Wang, Hong, Yan, Yong, “ORNL Interim Progress Report on Hydride Reorientation CIRFT Tests,” ORNL/TM-2016/660, November 2016.

15. Wang, Jy-An John, et al. FY 2016 Status Report: Documentation of All CIRFT Data including Hydride Reorientation Tests (Draft M2). ORNL/SR-2016/424. Oak Ridge, TN: Oak Ridge National Laboratory, September 2016.

16. Wang, Jy-An John and Hong Wang. FY 2016 Status Report: CIRFT Testing Data Analyses and Updated Curvature Measurements. ORNL/TM-2016/276. Oak Ridge, TN: Oak Ridge National Laboratory.2016.

17. Wang, Jy-An John and Hao Jiang. The Development of Expansion Plug Wedge Test for Clad Tubing Structure Mechanical Property Evaluation. ORNL/TM-2015/723. Oak Ridge, TN: Oak Ridge National Laboratory.2015.

18. Wang, Jy-An John, Hao Jiang and Hong Wang. Dynamic Deformation Simulation of Spent Nuclear Fuel Assembly and CIRFT Deformation Sensor Stability Investigation. ORNL/SPR-2015/662. Oak Ridge, TN: Oak Ridge National Laboratory.2015.

19. Wang, Hong, Jy-An John Wang and Fei Ren. Structural Health Monitoring of Compression Connectors in Overhead Transmission Lines Using a Smart Patch. LDRD Report. Oak Ridge, TN: Oak Ridge National Laboratory.2015.

20. Jy-An Wang, Hong Wang, Hao Jiang, and Yong Yan, “CIRFT Testing of High-Burnup Used Nuclear Fuel Rods from Pressurized Water Reactor and Boiling Water Reactor Environments,” M2-FCRD-UFD-2015-000101, September 2015.

21. Jy-An Wang, Hong Wang , Hao Jiang, “CIRFT Testing of Used Nuclear Fuel Rods from the Limerick Generating Station Boiling Water Reactor,” FCRD-UFD-2015-000635, April 2015.

22. Jy-An Wang, Hao Jiang, “BWR Spent Nuclear Fuel Interfacial Bonding Efficiency Study,” ORNL/TM-2015/269, June 2015.

23. Yong Chae Lim, Yanli Wang, Jian Chen, Jy-An Wang, Wei Zhang, Larry Anovitz, Zhili Feng, “Fracture Toughness and Fatigue Properties of Pipeline Base Steels and Welds in High-Pressure Hydrogen and Technologies for Improving Weld HE and IGSCC Resistance for Alternative Fuel Pipelines,” ORNL/TM-2014/707, December 2014.

24. Jy-An Wang, Hong Wang, Hao Jiang, Bruce Bevard, and Rob Howard, “CIRFT Testing Results on High Burnup UNF,” M2-FCRD-UFD-2014-000053, September 2014.

25. Jy-An Wang, Hong Wang, Hao Jiang, Bruce Bevard, Rob Howard, “Mechanical Fatigue Testing of High Burnup Fuel for Transportation Applications,” NUREG/CR report, ORNL/TM-2014/214, August, 2014.

26. Jy-An Wang, Hao Jiang, Bruce Bevard, John Scaglione, “Quantification of CIRFT System Biases and Uncertainties Associated When Testing High Burnup Spent Nuclear Fuel,” FCRD-UFD-2014-000604, September 2014.

27. Jy-An Wang and Hong Wang, “The Development of Reversible Bending Fatigue Tester and Its Application to High Burnup Spent Nuclear Fuel Vibration Integrity Investigation under Normal Transportation,” ORNL/TM-2013/573, August 2014.

28. Jy-An Wang, Hong Wang, and Hao Jiang, “Using Finite Model Analysis and Out of Hot Cell Surrogate Rod Testing to Analyze High Burnup Used Nuclear Fuel Mechanical Properties,” FCRD-UFD-2014-000603, August 2014.

29. Bruce Bevard, Jy-An Wang, et al., “FY 2014 Status Report: Vibration Testing of High Burnup Clad Fuel,” ORNL/LTR-2014/105, April 2014.

30. Jy-An Wang, et al., “2014 Semi-Annual Progress Letter Report on Used Nuclear Fuel Integrity Study in Transportation Environments,” ORNL/TM-2014/63, April 2014.

31. James Hemrick, Fei Ren, Dan Naus, Jy-An Wang, Sam Sham, “Performance and Reliability Enhancement of Concrete Confinement Structures for Nuclear Applications through Improved Concrete/Steel Interfacial Bonding,” LDRD Report 6679, September 2014.

32. Richard Howard, Yong Yan, Jy-An Wang, Larry Ott, and Rob Howard, “Post-Irradiation Examination of Zircaloy-4 Samples in Target Capsules and Initiation of Bending Fatigue Testing for Used Nuclear Fuel Vibration Integrity Investigations,” ORNL/LTR-2013/474, October 2013.

33. Harold Adkins, Ken Geelhood, Brian Koeppel, Justine Coleman, John Bignell, Gregg Flores, Jy-An Wang, Scott Sanborn, Robert Spears, Nick Klymshyn, “Used Nuclear Fuel Loading and Structural Performance Under Normal Conditions of Transport – Demonstration of Approach and Results on Used Fuel Performance Characterization,” FCRD-UFD-2013-000325, October 2013.

34. Jy-An Wang, Hao Jiang, and Hong Wang, “The Impact of Interface Bonding Efficiency on High Burn-up Spent Fuel Vibration Integrity during Normal Transportation,” ORNL/TM-2013/296, August 2013.

35. Jy-An Wang and Hong Wang, “Progress Report on Reverse Bending Fatigue Testing of Zry-4 Surrogate Rod,” ORNL/TM-2013/297, August 2013.

36. Jy-An Wang and Hong Wang, “Progress Letter Report on Bending Fatigue Test System Development for Spent Nuclear Fuel Vibration Integrity Study (Out-of-cell fatigue testing development - Task 2.4),” ORNL/TM-2013/225, July, 2013.

37. Zhili Feng, Wei Zhang, Jy-An Wang, Fei Ren, “Manufacturing Cost Analysis of Novel Steel/Concrete Composite Vessel for Stationary Storage of High-Pressure Hydrogen,” ORNL/TM-2013/113.

38. R.N. Morris, C.A. Baldwin, R. Battiste, J.M. Giaquinto, I.C. Gauld, J.G. Hemrick, K.J. Leonard, H.F. Longmire, W.J. McAfee1, J.K. McCoy2, J. Myers, S.L. Voit, J.-A. Wang, Y. Yan, “MOX PIE Fuel and Clad Examination Final Report,” ORNL/MD/LTR-352 Rev 2, May 2013.

39. Jy-An Wang and Hao Jiang, “Methodology for Mechanical Property Testing on Fuel Cladding Using a Modified Expansion Plug Testing Protocol,” ORNL/TM-2012/462, February 2013.

40. Jy-An Wang, Hong Wang, “Annual Progress Report on U-Frame Test Setup and Bending Fatigue Test for Vibration Integrity Study (Out-of-cell fatigue testing development - Task 2.3),” ORNL/TM-2012/417, December 2012.

41. Jy-An Wang, Fei Ren, H-L. Lee, “Improving Electrical Contact Conductivity via Surface Doping,” ORNL/TM-2012/356, October 2012.

42. Jy-An Wang, Ting Tan, Hao Jiang, Wei Zhang, Zhili Feng, “Developing Fatigue Pre-crack Procedure to Evaluate Fracture Toughness of Pipeline Steels Using Spiral Notch Torsion Test,” ORNL/TM-2012/337, October 2012.

43. Jy-An Wang, Hao Jiang, Fei Ren, “The Integrity of ACSR Full Tension Two-Stage Splice Connector at Higher Operation Temperature,” ORNL/TM-2012/323.

44. Jy-An Wang, Hao Jiang, Fei Ren, “The Integrity of ACSS Full Tension Two-Stage Splice Connector at Higher Operation Temperature,” ORNL/TM-2012/324.

45. Jy-An Wang, Ting Tan, Hao Jiang, Wei Zhang, Zhili Feng, “Developing Fatigue Pre-crack Procedure to Evaluate Fracture Toughness of Pipeline Steels Using Spiral Notch Torsion Test,” ORNL/TM-2012/337.

46. Jy-An Wang, Hao Jiang, Fei Ren, “The Integrity of ACSR Full Tension Two-Stage Splice Connector at Higher Operation Temperature,” ORNL/TM-2012/323.

47. Jy-An Wang, Hao Jiang, Fei Ren, “The Integrity of ACSS Full Tension Two-Stage Splice Connector at Higher Operation Temperature,” ORNL/TM-2012/324.

48. Jy-An Wang, James Hemrick, and Fei Ren, “Basic Research on the Materials Characterization of Ultra-High Performance Concretes: High Temperature and Rapid Heating,” ORNL/TM-2012/162, June 2012.

49. Jy-An Wang, Hong Wang, et al., “Progress Letter Report on U-Frame Test Setup and Bending Fatigue Test for Vibration Integrity Study,” ORNL/TM-2011/531, May 2012.

50. Jy-An Wang, “Review of the Atucha-I Reactor Pressure Vessel Surveillance Program,” ORNL/TM-2011/500, December 2011.

51. Jy-An Wang, Fei Ren, Ting Tan, John Mandell, Pancasatya Agastra, “An Innovative Technique for Evaluating the Integrity and Durability of Wind Turbine Blade Composites - Final Project Report,” ORNL/TM-2011/449, November 2011.

52. Wang, Jy-An John, et al. Review on Atucha-I Reactor Pressure Vessel Surveillance Program - Phase I Progress Letter Report. ORNL/LTR-2011/334. Oak Ridge, TN: Oak Ridge National Laboratory.2011.

53. Jy-An Wang and Hong Wang, "Spent Fuel Vibration Integrity Project Progress Report," ORNL/TM-2010/288, January, 2011.

54. Jy-An Wang, Ting Tan, and Hong Wang, “3-D FEM Simulation of the Proposed Dynamic Bending Fatigue Tester for Spent Fuel Vibration Integrity Program,” ORNL/TM Report.

55. J-A. Wang and F. Ren, “Evaluation of High Temperature Integrity of ACSR Two-Stage Splice Connectors and Development of Next Generation Advanced Connectors”, ORNL Report ORNL/TM-2010/340, Oak Ridge National Laboratory, 2010.

56. Jy-An Wang, Fei Ren, John Mandell, “FY11 Q1 Progress Report - An Innovative Technique for Evaluating the Integrity and Durability of Wind Turbine Blade Composites Project,” ORNL/TM-2010/333, January 2011.

57. Jy-An Wang and Hong Wang, “Spent Nuclear Fuel Vibration Integrity Study Progress Report,” ORNL/TM-2010/288, May 2011.

58. Jy-An Wang and Fei Ren, "Thermal and Mechanical Characterization of Advanced Concrete Materials," ORNL/TM-2010/267, October 2010.

59. Jy-An Wang, Catherine Mattus, and Fei Ren, "DHS counter Improvised Explosive Device Effects Basic Research Project FY10," ORNL/TM-2010/227, September 2010.

60. John Jy-An Wang and Fei Ren, “An Innovative Technique for Evaluating the Integrity and Durability of Wind Turbine Blade Composites”, ORNL Report ORNL/TM-2010/191, Oak Ridge National Laboratory, 2010.

61. Jy-An Wang, "Review on MHI US-APWR Containment Performance for Pressure Loads," NRC letter report, August, 2010.

62. Jy-An Wang, "Review on Root Cause Assessment of Crystal River Unit 3 Containment Concrete Delamination," NRC letter report, July 2010.

63. Jy-An John Wang, "Lessons Learned From Developing Reactor Pressure Vessel Steel Embrittlement Database," ORNL/TM-2010/20, August, 2010.

64. Jy-An Wang, Catherine Mattus, and Fei Ren, "DHS counter Improvised Explosive Device Effects Basic Research Project," ORNL/TM-2009/317, July 2010.

65. Jy-An Wang, Fei Ren, and Hong Wang, "An Innovative Low/High Temperature Repetitive Pressure-Pulse Apparatus for Cavitation Damage Research," ORNL/TM-2009/260, December 2009.

66. Jy-An Wang, "Investigation of Pipelines Integrity Associated with Pump Modules Vibration for Pumping Station 9 of Alyeska Pipeline Service Company," ORNL/TM-2009/254, October 2009.

67. Jy-An Wang, "The Embrittlement Trend Curve Study for HFIR Reactor Pressure Vessel Steels," ORNL/TM-2009/152, currently is still under review by HFIR RPV Integrity Surveillance Team.

68. Jy-An Wang, Catherine H. Mattus, and Fei Ren, "DHS counter Improvised Explosive Device Effects Basic Research Project," ORNL-TM-2009/317, December 2009.

69. Jy-An Wang, Fei Ren, and Hong Wang, "An Innovative Low/High-Temperature, Repetitive Pressure-Pulse Apparatus for Cavitation Damage Research," ORNL/TM-2009/260, November, 2009.

70. Jy-An Wang, "Investigation of Pipelines Integrity Associated with Pump Modules Vibration for Pumping Station 9 of Alyeska Pipeline Service Company," ORNL/TM-2009/254, October, 2009.

71. Jy-An Wang, "The Embrittlement Prediction Trend Curve Development for HFIR Reactor Pressure Vessel Steels," ORNL/TM-2009/152, June 2009.

72. John Jy-An Wang, Edgar Lara-Curzio, Thomas King, and John Chan, "Methodology for Predicting the Service Life of HTLS Conductors: The Integrity of ACSR Full Tension Single-Stage Splice Connectors at Higher Operation Temperatures," EPRI-1018626, Electric Power Research Institute, Palo-Alto, March 2009.

73. Jy-An Wang, 2009 R&D 100 Awards application, " MELCOT: Methodology for Estimating the Life of Conductor-Connector Systems Operating at High Temperatures," February 2009.

74. Jy-An Wang, Edgar Lara-Curzio, and Tom King, "The Integrity of ACSR Full Tension Single-Stage Splice Connector at Higher Operation Temperature," ORNL/TM-2008/156, September 2008.

75. John Jy-An Wang, Ken C. Liu, Dan Naus, " Developing An Innovative Field Expedient Fracture Toughness Testing Protocol For Concrete Materials," ORNL/TM-2008/155, September 2008.

76. Jy-An Wang, "Preliminary Investigation on Alyeska’s PS09 SR Modules Piping Reports and the Site Visit," ORNL Letter report, November 2007.

77. 4. Jy-An Wang, "Review Comments on EDI Report 93393-1 Regarding PS09 and PS03 Vibration Investigation," ORNL Letter report, June 2008.

78. Three disclosure reports on subject related to Design new apparatus for in-situ hydrogen tensile, torsion, and fatigue testing under high pressure.

79. J. A. Wang, S. Ranjit, “PR-EDB: Power Reactor Embrittlement Database Version 3,” ORNL/TM-2006/605, 2008. 

80. Jy-An Wang, “An Innovative Low/High-Temperature, Repetitive Pressure-Pulse Apparatus for Cavitation Damage Research,” ORNL LDRD-S07-050, October 2007.

81. J. A. Wang, DOE Annual Report on Power Transmission, “Methodology for Predicting the Service Life of High-temperature Low-sag Conductors (HTLS),” September 2007.

82. J. A. Wang, “Progress Report on High Temperature Low-Sag Power Conductor Material Lifetime Estimate Project,” March 2006.

83. J. A. Wang, “Background Review of Inelasticity and Plasticity and the Constitutive Models Used in CTH Hydro Code,” ORNL/LTR/NR-PROM1/05-03, June 2005.

84. J. A. Wang, et.al. “An Innovative Technique for Thin Film Interface Toughness Research, ORNL/TM-2004/221, October 2004.

85. J. A. Wang, “ARN-Atucha-I RPV Embrittlement,” ORNL report, 2004.

86. J. A. Wang, “Verification of EPRI new BWR Database,” NRC letter report, December 2003.

87. J. A. Wang, “Integrity of Atucha-I NPP Surveillance Program,” ORNL-FTR-155634, 2002.

88. J. A. Wang and K. C. Liu, “The Development and Methodology of ORNL Spiral Notch Torsion Test (SNTT) Technology,” ORNL report to 2002 R&D 100 Awards, March 2002.

89. J. A. Wang and K. C. Liu, “Fracture Toughness Determination Using Spiral-Grooved Cylindrical Specimen and Pure Torsional Loading,” submitted in June 2001 for U.S. Patent Application.

90. J. A. Wang, “TOR3D-KIC: A 3-D Finite Element Analysis Code for Determination of Fracture Toughness, KIc, for Spiral Notch Torsion Fracture Test (SNTT),” ORNL LTR report, Oct. 2001.

91. R. K. Nanstad, W. R. Corwin, R. E. Stoller, J. A. Wang, and D. E. McCabe, "Assessment of Material Embrittlement of Surveillance Specimens for the KKS Reactor Pressure Vessel," ERD-96-1382, 2000.

92. J. A. Wang, F.B.K. Kam, “Review of the International Atomic Energy Agency International Aging Database on Reactor Pressure Vessel Materials and U.S. Nuclear Regulatory Commission/Oak Ridge National Laboratory Embrittlement Data Base,” ORNL/NRC/LTR-97/25, February 1998.

93. J. A. Wang, “Embrittlement Data Base, Version 1,” NUREG/CR-6506, ORNL/TM-13327, Nuclear Regulatory Commission, 1998.

94. J. A. Wang, K. C. Liu, D. E. McCabe, and S. A. David, “An Innovative Small Specimen Testing Technique for the Determination of Fracture Toughness,” ORNL/M-6366, 1999.

95. J. A. Wang, “Analysis of the Irradiated Data for A302B and A533B Correlation Monitor Materials,” NUREG/CR-6413, ORNL/TM-13133, Nuclear Regulatory Commission, April 1996.

96. R. K. Nanstad, W. R. Corwin, R. E. Stoller, J. A. Wang, and D. E. McCabe, “ Assessment of Material Embrittlement of Surveillance Specimens for the German KWO Reactor Pressure Vessel,” ERD-95-1317, 1995.

97. R. K. Nanstad, D. J. Alexander, W. R. Corwin, E. D. Eason, G. R. Odette, R. E. Stoller, and J. A. Wang, “Review of Data Regarding Chemical Composition and Thermal Embrittlement of Reactor Vessel Steels,” ORNL/NRC/LTR-95/1, NRC JCN No. L1098, Nuclear Regulatory Commission, 1995.

98. J. A. Wang, "Charpy Impact Curve Fitting with Chemistry Adjustment to Reduce Uncertainty" letter report to ASTM E10.02 Committee, presented at Phoenix ASTM committee meeting, 1995.

99. J. A. Wang, "A better Correlation Index for the Radiation Embrittlement," letter report to ASTM E10.02 Committee, presented at Phoenix ASTM committee meeting, 1995.

100. F. W. Stallmann, J. A. Wang, F. B. K. Kam, "TR-EDB: Test Reactor Embrittlement Data Base, Version 1," NUREG/CR-6076, ORNL/TM-12415, Nuclear Regulatory Commission, January 1994.

101. F. W. Stallmann, J. A. Wang, F. B. K. Kam, B. J. Taylor, "PR-EDB: Power Reactor Embrittlement Data Base, Version 2," NUREG/CR-4816, ORNL/TM-10328/R2, 1994.

102. J. A. Wang, F. B. K. Kam, and F. W. Stallmann, “PT_LIM: A Computer Program to compute Pressure-Temperature Limits for U.S. Power Reactor,” NUREG/CR-6019, ORNL/CAD/TM-286, Nuclear Regulatory Commission, 1993.

103. J. A. Wang, “Damage Exposure Unit (Displacement per Atom) for RPV Supporting Structure,” ORNL letter report, 1991.

104. J. A. Wang, “Comment to the Cesium-137 Capsule on Thermal Analysis, Corrosion and Radiation Damage”, ORNL letter report, 1990.

105. P. N. Randall, F. B. K. Kam, and J. A. Wang, “Effects of Phosphorus on the Transition Temperature Shift of Charpy Impact Test Data.” Letter report to ASTM E10.02 Committee, 1989.

106. J. A. Wang, “Embrittlement Data Base (EDB) User Manual.” NRC letter report, 1989.

107. J. A. Wang, “Comparison of the EDB Program, Charpy Impact Data Fitting to the TANH Program of the EPRI Steel Handbook,” TENERA Project, 1989.

108. J. A. Wang, "Semi-Analytical Method for the Analysis of Torsional Soil Structure Interaction," University of California, Berkeley, report, 1984.

109. J, A. Wang, “The Modified Direct Method for the Calculation of the Elastic Moduli of Composite Materials,” Ph.D. Thesis, 1988, University of California, Berkeley.

Technical Presentations:

1. Presented “Monitoring Structural Health of High Voltage Transmission Lines,” in Edison Electric Institute (EEI/GMLC) Wildfire Mitigation Capabilities Initiative, July 23, 2020.

2. Presented “Surrogate Spent Nuclear Fuel Vibration Integrity Investigation,” 2014 ANS Annual Meeting, June 15-19, 2014, Reno Nevada.

3. Presented “Potential Effect of Interfacial Bonding on Used Nuclear Fuel Vibration Reliability,” 2014 ANS Annual Meeting, June 15-19, 2014, Reno Nevada.

4. Presented “Potential Impact of Interfacial Bonding Efficiency on High-Burnup Spent Nuclear Fuel Vibration Integrity during Normal Transportation,” WM2014 International Conference, Phoenix, AZ, March 02-06, 2014.

5. Presented “Reversible Bending Fatigue Testing on Zry-4 Surrogate Rods,” Wm2014 International Conference, Phoenix, AZ, March 02-06, 2014.

6. Presented “Reversal Bending Fatigue Test System for Investigating Vibration Integrity of Spent Nuclear Fuel during Transportation,” Proceedings of the 17th International Symposium on the Packaging and Transportation of Radioactive Materials PATRAM 2013, August 18-23, 2013, San Francisco, CA.

7. Presented “The Development of Reversal Bending Fatigue Tester for Spent Nuclear Fuel Vibration Integrity Study,” Used Fuel Disposition Campaign WG Meeting on UNF NCT Loading & Structural Performance May 22, 2013, UNLV, Las Vegas, Nevada.

8. Presented “Spent Nuclear Fuel Test System for Bending Stiffness and Vibration Integrity,” 2013 International High-Level Radioactive Waste Management Conference, April 28- May 2, 2013, Albuquerque, New Mexico.

9. Presented “Methodology for Predicting the Service Life of ACSR/ ACSS-TSC Connector Fitting,” EPRI HTLS Program Review Meeting, EPRI Dallas Office, April 23-24, 2013, Texas.

10. Presented “Spiral notch torsion test for fracture toughness evaluation of polymeric composite materials,” Disbond/Delamination TG Meeting, The Composite Materials Handbook CMH-17 Meeting, Seattle, WA – April 8-11, 2013.

11. Presented “Methodology for Developing Benchmark/ Calibration Data to Support Spent Nuclear Fuel Reliability Investigation under Random Vibration Loadings Using Reversal Bending Fatigue Tester,” US DOE, NNSA Nevada Site Office, UNF Performance M&S and Experimental Integration Implementation Team Working Meeting, February 21-22, 2013

12. F. Ren, Y. Liu, H. Wang, and J-A. Wang, “Development of an erosion/corrosion protocol to evaluate the behavior of casing materials”, 2012 MRS Fall Meeting, Boston, MA, Nov. 25 – 30, 2012.

13. H. Jiang, J-A. Wang, and F. Ren, “Integrity Study of ACSR and ACSS Two Stage Splice Connectors at High Operation Temperatures”, ASME 2012 International Mechanical Engineering Congress & Exposition, Houston, TX, November 9-15, 2012.

14. W. Zhang, F. Ren, Z. Feng, J.A. Wang, H. Y. Song, S. S. Babu, M. Boring, L. Hayden, and J. Merrit, “Microstructure of High-Strength Pipeline Steel Welds and their Resistance to Hydrogen Embrittlement”, 9th International Pipeline Conference, Calgary, Alberta Canada, September 24-28, 2012.

15. J-A Wang, F. Ren, and T. Tan, “Spiral Notch Torsion Test for Determining Fracture Toughness of Structural Materials”, ASME 2012 Pressure Vessels and Piping Conference, Toronto, Canada, July 15-19, 2012.

16. Presented “Development of a Pulsed Pressure-Based Technique for Cavitation Damage Study”, 8th International Symposia on Cavitation, Singapore, August 14-16, 2012.

17. S. Voisin, F. Ren, H. Z. Bilheux, J-A Wang, and B. P. DiPaolo, “Neutron Imaging of Ultra High Performance Concrete”, American Conference on Neutron Scattering, Washington DC, June 24-28, 2012.

18. Presented “A new Approach to Determine the Quasi-static and Dynamic Fracture Toughness of Materials,” SEM XII International Congress & Exposition on Experimental & Applied Mechanics, Orange County/Costa Mesa, June 11-14, 2012.

19. T. Tan, J-A. Wang, F. Ren, E. Lara-Curzio, P. Agastra, J. Mandell, W. D. Bertelsen, and C. M. LaFrance, “Study of Fracture Behavior of Epoxy and Composite Materials for Wind Turbine Blades Using Spiral Notch Torsion Test”, 2012 Windpower Conferences and Exhibition, Atlanta, GA, June 3 – 6, 2012.

20. Presented “Spiral notch torsion test for fracture behavior evaluation of polymeric composite materials for wind turbine applications”, Materials Challenges in Alternative and Renewable Energy, Clearwater, FL, February 26 – March 1, 2012.

21. Presented “Evaluation and improvement of conductor connectors for electrical power transmission system”, Materials Challenges in Alternative and Renewable Energy, Clearwater, FL, February 26 – March 1, 2012.

22. W. Zhang, Z. Feng, F. Ren, J-A Wang, and L. Anovitz, “Susceptibility of Carbon Steel Welds to Hydrogen Embrittlement”, FABTECH 2011 - AWS Professional Program, Nov. 13, 2011

23. F. Ren, J. A. Wang, T. Tan, E. Lara-Curzio, P. Agastra, J. Mandell, W. D. Bertelsen , and C. M. LaFrance, “Fracture study of polymer and polymeric composite materials using the spiral notch torsion test”, Materials Science and Technology 2011 Conference, Columbus, OH, October 16-20, 2011.

24. Presented “Fracture behavior of polymer polymeric composite materials under mixed mode loading using the spiral notch torsion test”, 6th International Conference on Fracture of Polymers, Composites and Adhesives, Les Diablerets, Switzerland, Sep. 11-15 2011.

25. F. Ren, C. Mattus, J. A. Wang, and B. DiPaolo, “Microstructural characterization of UHPC materials subject to impact testing and heating”, The 2nd Advances in Cement-based Materials Conference, Nashville, TN, July 24-26, 2011.

26. Presented “Study of the Effect of Welding on the Fracture Behavior of 4340 Steel Using Spiral Notch Torsion Test (SNTT)”, ASME 2011 Pressure Vessels and Piping Conference, Baltimore, MD, July 17-21, 2011.

27. F. Ren, J-A. Wang, and Bill Bertelsen, “Fracture behavior study of polymeric materials for wind turbine blades using the spiral notch torsion test”, Materials Science and Technology 2010 Conference, Houston, TX, October 17-21, 2010.

28. Presented “MELCOT System program development” at Nexans, Brussels, Belgium, March 8, 2011.

29. Presented “An innovative repetitive pressure pulse device for cavitation damage research,” in ONR sponsored International Cavitation Research Workshop, Grenoble University, France, March 1-2, 2011.

30. Present “Spiral Notch Torsion Program Development and Its Application to Hydrogen Embrittlement,” Air Liquide Research Center, Paris, France, March 4, 2011.

31. Attended and presented ORNL Hydrogen Embrittlement Program at DOE Hydrogen Program workshop sponsored by Sandia Lab, November 2011.

32. Present 2-stage Splice connector 3-D forming simulation at EPRI HTLS program review meeting, October, 2010, Palo Alto, California.

33. Presented "An Innovative Repetitive Pressure Pulse Device for Cavitation damage research," at 2010 ASME PVP Conference, Seattle, WA, July 2010.

34. Presented "Advanced Connector Program Development," at DOE/OE Peer Review Meeting, Washington DC, July 2010.

35. Present "MELCOT System program development," at Charlotte, NC, EPRI Headquarter, April 2010.

36. Presented "Ultra-high Performance Concrete Characterization," at DHS program review meeting, Feb 2010, Georgia Tech, Atlanta, GA.

37. Presented "Materials Performance & Structure Components Long-term Reliability," at DHS Infrastructure and Civil Structural Integrity Forum, Oak Ridge, TN, August 13, 2009.

38. Presented "A Novel Approach for Cavitation Damage Research," at DHS Infrastructure and Civil Structural Integrity Forum, Oak Ridge, TN, August 13, 2009.

39. Presented "UHPC/RPC Materials Microstructure Characterization," at DHS cIED Basic Research Project Kick-off Meeting, Georgia Tech, Atlanta, Georgia, July 10, 2009.

40. Presented "To Increase Power Transmission Efficiency By Increase Surface Conductance," at EPRI HTLS Conductor Program Review Meeting, Atlanta, March 10-11, 2009.

41. Presented, "The Effective Lifetime of ACSR Full Tension Splice Connector Operated at Higher Temperature, in 2009 IEEE TP&C Joint Meeting (Conductor Working Group meeting), January 12-15, 2009, Atlanta, GA.

42. To present "SNTT Program Development and Its Application to the Integrity Study of Reactor Pressure Vessel Internal," at EPRI, Palo Alto, California, December 18, 2008.

43. To present SNTT program development at John A. Blume Earthquake Engineering Center of Civil Engineering Department, Stanford University, Palo Alto, California, October 10, 2008.

44. Presented "Applying SNTT To The HAZ of Weldment and Rock Integrity Investigation," at Yucca Mountain Project of Bechtel Inc., Las Vegas, NV, October 7, 2008.

45. Presented, "The program development of effective lifetime of ACSR connector system operated at high temperature," in 2008 ANSI C119 committee meeting, Las Vegas, NV, October 6, 2008.

46. Presented, "Effective lifetime estimate of crimped power line splice connector operated at high temperature," in 2008 ASME PVP Conference, July 28, 2008, Chicago, IL.

47. Presented “Methodology for Estimating Effective Lifetime for ACSR Full-tension Splice Connector Operated at High Temperature,” at DOE Peer-review meeting, DOE Headquarter, October 21, 2008, Washington DC.

48. Presented “Effective Lifetime prediction models for ACSR Single stage splice connector operated at high temperature,” at EPRI Dallas's Office, July 29, 2008, Dallas, TX.

49. Presented “Thermal cycle and water quenching effect to the effective lifetime of ACSR Single stage splice connector,” at SDG&E, San Diego, February, 20, 2008.

50. Presented “Thermal cycle effect to the effective lifetime of ACSR Single stage splice connector,” at 3M Headquarter, September 24, 2007, San Paul, Minnesota.

51. Presented “Interface Fracture Toughness Investigation,” at 3M Headquarter, September 24, 2007, San Paul, Minnesota.

52. Presented “The Integrity of ACSR Full Tension Splice Connector at Higher Operation Temperature,” 2007 IEEE Power Engineering Society General Meeting Conference, Tampa Florida, June 24-28, 2007.

53. Presented "The Compressive Residual Stress Degradation of SSC System under thermal cycling," at EPRI, Charlotte, North Carolina, April 29, 2007.

54. Presented "The Integrity of ACSR SSC system operated at high temperature," in ASC C119 Committee meeting, April 16, 2007, Daytona Beach, Florida.

55. Presented “An Innovative Small Specimen Technique for Evaluating Fracture Toughness of Structural Materials,” ASTM Fifth Symposium on Small Specimen Test Techniques, January 31-February 1, 2007, Anaheim, California.

56. Presented "Residual Stress Evaluation within a Crimped Splice Connector Assembly," 2006 Electrical Transmission Conference, October 15-19, 2006, Birmingham, Alabama.

57. Presented, “An innovative Fracture Toughness Test for Graphite Materials,” 7th International Nuclear Graphite Specialists Meeting, September 10-13, 2006, Oak Ridge, Tennessee.

58. Presented “Spiral Notch Torsion Test (SNTT) Technology,” to Medtronic Inc., Columbia Height, NM, June 2006.

59. Presented “The Information Fusion Embrittlement Models for U.S. Power Reactor Pressure Vessel Steels,” The Effects of Radiation on Materials: ASTM 23rd International Symposium & JAI, May 2006, San Jose, California.

60. Presented “Atucha-I Surveillance Program Proposal,” at DOE Headquarters, Washington DC, October 6, 2005.

61. Presented “Interface Fracture Toughness Evaluation for MA956 Oxide Film,” in 2005 ASM International Surface Engineering Congress, August 1-3, 2005, St. Paul, Minnesota.

62. Presented “Determination of Interfacial Fracture Toughness for Thin Film Coating Materials,” in 2005 ASME Pressure Vessel Piping Conference, July 17-21, 2005, Denver, Colorado.

63. Presented “Information Fusion Method for Estimating Radiation Embrittlement of Reactor Pressure Vessel Steels,” 13th International Conference on Nuclear Engineering, Beijing, China, May 16-20, 2005.

64. Presented “An Innovative Technique for Bi-Material Interface Toughness Research,” in 2004, ASME International Mechanical Engineering Congress, November 13–19, 2004, Anaheim, California.

65. Presented “A New Approach for Evaluating Radiation Embrittlement of Reactor Pressure Vessel Steels,” in 2004 ASME Pressure Vessel and Piping, July 23, 2004, San Diego, California.

66. Presented “A New Approach To Evaluate Fracture Toughness of Structural Materials,” in 2003 ASME Pressure Vessel and Piping, July 21-24, 2003, Cleveland, Ohio.

67. Co-chair a one-day special session on “Reactor Pressure Vessel Embrittlement” in 2003 ANS Annual Meeting. Presented “A New Methodology for Developing Charpy Impact Data Trend Curves,” in 2003 ANS Annual Meeting, June 1-4, 2003, San Diego California.

68. Invited by Vanderbilt University to give a seminar on “The development of Spiral Notch Torsion Test Technology,” September 30, 2002, Nashville, Tennessee.

69. Invited by Material Science and Technology Division of Los Alamos National Laboratory to present “An Innovative Technique for Measuring Fracture Toughness,” August 13-14, 2002, Los Alamos, New Mexico.

70. Presented “Radiation Embrittlement Prediction Models and the Impact of Irradiation Temperature,” at ASTM 11th International Symposium on Reactor Dosimetry ISRD’2002 Conference, Brussels, August 18-23, 2002.

71. Presented “Using Torsion Bar Testing to Determine Fracture Toughness of Ceramic Materials,” at ASME ETCE 2002 Conference, February 3-4, 2002, Houston, Texas.

72. Presented “Radiation Effects on Spacecraft Structural Materials,” at ANS International Conference on Advanced Nuclear Power Plants, June 9-13, 2002, Hollywood, Florida.

73. Presented “New Methodologies for Developing Radiation Embrittlement Models and Trend Curves of the Charpy Impact Test Data,” at ASTM 21st Symposium on Effects of Radiation on Materials, Tucson, Arizona, June 18-20, 2002.

74. Invited by SRS Strategic Materials Technology Department to present “Using Torsion Bar Testing to Determine Fracture Toughness,” at DOE SRS site on August 14, 2001.

75. Presented “An Innovative Technique for Measuring Fracture Toughness of the Metallic and Ceramic Materialsals,” at the 33rd ASTM National Symposium on Fatigue and Fracture Mechanics, June 26-29, 2001, Moran, Wyoming.

76. Presented “Using Torsion Bar Testing to Determine KIC,” at Stanford Research Institute (SRI International), February 2001, Menlo Park, California.

77. Presented “An Innovative Small Specimen Testing Technique,” at 4th ASTM Small Specimen Symposium sponsored by ASTM E10 committee, January 18-21, 2001, Reno, Nevada.

78. Presented “On the Effectiveness of A Multiaxial Fatigue-Life Predictive Method Based on A Virtual Strain-Energy (VSE) Concept,” at the International Conference on Fatigue Damage of Structural Materials III, on September 18-22, 2000, Hyannis, Massachusetts.

79. Presented “Using Torsion Bar Testing To Determine Fracture Toughness KIC,” at Naval Research Laboratory (NRL) on June 1, 2000, Washington D.C.

80. Presented “The Development of Torsion Bar Testing for the Determination of KIC Fracture Toughness,” at Turner-Fairbanks Research Center (TFRC) of DOT, McLean, Virginia, 2000.

81. Presented “An Innovative Testing Technique for Determining Fracture Toughness, and Its Potential Application to the Aggregate Composites,” to Advanced Cement Based Materials (ACBM) NSF Center at Northwestern University, February 4, 2000.

82. Presented “Using Torsion Bar Testing to Determine Fracture Toughness, and Its Potential Application to Inhomogeneous Materials,” at Air Force Office of Scientific Research (AFOSR), Falls Church, Virginia, January 7, 2000.

83. Presented “Using Torsion Bar Testing to Determine Fracture Toughness,” and “Integrated Distributed Database Management System and the Development of Embrittlement Prediction Models for U.S. Power Reactor Pressure Vessel Steels,” at the workshop of Naval Materials by Design, sponsored by the Office of Naval Research at Alexandria, Virginia, January 6–7, 2000.

84. Presented “U.S. NRC Embrittlement Data Base (EDB),” at ASTM 10th International Symposium on Reactor Dosimetry, September 12-17, 1999, Osaka, Japan.

85. Presented “Analysis of the Irradiated Data for A302B and A533B Correlation Monitor Materials,” at ASTM 19th Symposium on Effects of Radiation on Materials, June 16-18 1998, Seattle Washington.

86. Presented “Development of Embrittlement Prediction Models for U.S. Power Reactors and the Impact of the Heat-Affected Zone to Thermal Annealing,” at ASTM 18th Symposium on Effects of Radiation on Materials, June 21-25, 1996, Hyannis, Massachusetts.

87. Presented “Using Ultrasonic Measurements and a Two-Phase Composite Model to Assess Radiation Damage in Reactor Pressure Vessel Steels,” at ASTM symposium on Nontraditional Methods of Sensing Stress, Strain, and Damage in Materials and Structures, Orlando, Florida, May 6-11, 1996.

88. Presented “The Modified Direct Method for the Calculation of the Elastic Moduli of Composite Materials," at the First International Conference on Composites in Infrastructure, Tucson, Arizona, January 16-20, 1996.

89. Presented "Charpy Impact Curve Fitting with Chemistry Adjustment to Reduce Uncertainty" and “A better Correlation Index for the Radiation Embrittlement,” at Phoenix ASTM E10.02 subcommittee meeting, 1995.

90. Presented “Embrittlement Data Base (EDB) and Its Applications,” at ASTM 17th Symposium on Effects of Radiation on Materials, Sun Valley, Idaho, June 20-23, 1994.

91. Presented “Embrittlement Database Management,” at NRC Program Review, and at ETTC 1994.

Organized Conferences/workshops Related Activities

From 2004-2019 served as subcommittee member of ASME PVP-MF-2; organized annual ASME Pressure Vessel Piping Conference for Manufacturing & Fabrication Division since 2004.

From 2008-2011 served as committee member of DHS Advanced Material Council; assisting annual DHS Infrastructure workshop and AMC advanced material database development.

From 2008-present served as subcommittee member in IEEE/PES, ANSI C119, to develop connector standard.

From 1989-2008 served as subcommittee member of ASTM E10.02; represented NRC to participated semi-annual E10.02 committee meeting related to power reactor embrittlement database development. I had coordinated and organized forums with power utilities, academic and research institution to develop PR-EDB and TR-EDB in assisting the development of Reactor Pressure Vessel embrittlement trend curves for US nuclear industry and regulatory body; and provided assistance in organizing the ASTM E10 Symposiums on “Effects of Radiation on Materials.”

Awards and Professional Association Memberships

Received 2009 R&D 100 Awards for developing MELCOT System

Received 2002 R&D 100 Award for developing SNTT Technology.

Received 2004 Significant Accomplishment Award from NSTD division of ORNL.

Received 2003 Best Paper Award from ASME PVP Division.

Received recognition of work on Atucha-I surveillance from Argentina Nuclear Authority, 2002.

Received recognition of work on German KWO project from German Utility, 1995.

Received an excellence performance remark on NRC subcontracted EDB Program work, 1994.

Received U.C.B. Popert Fellowship Fund, 1984-1985.

Received U.C.B. Chancellor's Patent Fund, 1982-1983.

American Society for Testing and Materials, E10.02 subcommittee member.

American Society of Mechanical Engineers, PVP M-F subcommittee member.

IEEE Power Engineering Society member

American Society of Civil Engineers.

American Nuclear Society.

ASM International (The Materials Information Society)

P. E. License in the field of Mechanical Engineering.

P. E. License in the field of Structural I.

US Patent

1. U.S. Patent No. 10,578,533, Jy-An Wang, et.al., Issued: March 3, 2020, “Specimen for evaluating pressure pulse cavitation in rock formation.”

2. U.S. Patent No. 9,574,431, Jy-An Wang, et.al., Issued: February 21, 2017, “Cavitation-Based Hydro-Fracturing Technique for Geothermal Reservoir Stimulation.”

3. U.S. Patent No. 9,562,646, Issued: February 7, 2017, “Hydrogen Storage Container.”

4. US Patent 9,413,092, August 11, 2016, J. Chan, J-A Wang, F. Ren, “Improved Electrical Contact Conductivity via Surface Doping.”

5. US Patent 9,500,068 B2, Jy-An Wang, et al., “A Cavitation-Based Hydro-Fracturing Simulator,” November 22, 2016.

6. US Patent No. 8,664,529, Jy-An Wang, et.al., Issued: March 4, 2014, “Ultra High Performance Connectors for Power Transmission Applications.”

7. US Patent No. 8,863,585 B2, Oct. 21, 2014, Jy-An Wang, Hong Wang, and Ting Tan, “Reversal Bending Fatigue Testing.”

8. US Patent 6588283, Wang, J-A., Liu, K., “Fracture Toughness Determination Using Spiral-Grooved Cylindrical Specimen and Pure Torsional Loading,” July 8, 2003.

9. US Patent 8,176,795 B2, Wang, J-A., et al., “Apparatuses for prestressing rod-type specimens in torsion for in-situ passive fracture toughness testing in an extremely high-pressure environment of hydrogen,” May 15, 2012.

10. US Patent 8,230,748 B2, Wang, J-A., et al., “Apparatus for pre-straining rod-type specimens in tension for in-situ passive fracture testing,” Jul 31, 2012.

11. U.S. Patent 8,453,515 B2, Jy-An Wang, et al., "Apparatus and method for fatigue testing of a material specimen in a high-pressure fluid environment," June 4, 2013.

US Patent Pending

1. ORNL Invention Disclosure-2882, “Structural Health Monitoring of Compression Connector Using Electromechanical Impedance Analysis,” January 2017.

Invention Disclosure

1. ORNL Invention Disclosure- 201603785, DOE S-138,434, “Advanced Damping System to Reduce Fuel Assembly Contact Interaction Intensity within a Spent Nuclear Fuel Transport Cask,” October 25, 2016.

2. ORNL Invention Disclosure- 201603791, DOE S-138,440, “Using a Smart Patch to Monitor the Structural Health of Compression Connectors in Overhead Transmission Lines,” October 25, 2016.

3. ORNL Invention Disclosure-201202886, “Mechanical Property Testing on Fuel Cladding Using Modified Expansion Plug,” June 21, 2012.

4. ORNL Invention Disclosure-2887, “A Method for Evaluating the Crack Growth in Spiral Notch Torsion Test,” July 2012.

5. ORNL Invention Disclosure-201202909, “Testing of Spent Nuclear Fuel with Pneumatically-Driven Fixture,” July 2012.

Received A Significant Event Award from ORNL for developing CIRFT in 2014.

Received NRC Spent Fuel Vibration Integrity fund 2011-2014.

Received DOE UFDC fund 2013-2014.

Received DOE EERE/Geothermal Program fund 2011-2012.

Received DHS fund on ultra-high performance concrete, RPC behavior under fire, 2011.

Received EPRI TI & HTLS Program fund 2011-2013 for advanced connector development.

Received DOE/OE Advanced Conductor-Connector Program Fund 2010.

Received NRC SNF Program fund 2010 and NRC NRR Program fund 2008-2010.

Received DOE/Geothermal Program Fund in November 2010.

Received Army Corps of Engineer and DHS fund on the proposed counter IED Basic Research project, 2009-2010.

Received DOE Wind Power program fund on the proposed wind turbine blade reliability research, 2009-2010.

Received ARN fund for the proposed RPV steel surveillance program. 2008-2010.

Received DOE/OE Program funds for the submitted proposals related to energy efficiencies and alternative energy initiative since 2007-2010.

Received EPRI/HTLS program Fund from 2006-2010 on the proposed project of developing ACSR conductor-connector system reliability under high temperature operation.

Received DOT PHMSA fund 2007.

Received NRC fund for new reactor licensing review, since 2006.

Received RIST fund since 2004.

Received NRC fund for PR-EDB Program 2005-2007.

Received ORNL/LDRD Seed Program Fund on proposed projects in 1998, 2000, 2003, 2007, 2008.

Received ORNL/LTR Program Fund in 2001, and 2002 DOE RAP research program.

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