Jy-An Wang | Oak Ridge National Laboratory (original) (raw)

Papers by Jy-An Wang

Research paper thumbnail of Fracture toughness evaluation for thin-shell stainless steel weldment

Theoretical and Applied Fracture Mechanics

Research paper thumbnail of High burn-up spent nuclear fuel transport reliability investigation

Nuclear Engineering and Design

Research paper thumbnail of Using Torsion Bar Testing to Determine Fracture Toughness of Ceramic Materials

Research paper thumbnail of U.S. NRC Embrittlement Data Base (EDB)

Reactor Dosimetry: Radiation Metrology and Assessment, 2001

Large amounts of data obtained from surveillance capsules and test reactor experiments are needed... more Large amounts of data obtained from surveillance capsules and test reactor experiments are needed, comprising many different materials and different irradiation conditions, to develop generally applicable damage prediction models that can be used for industry standards and regulatory guides. Version 1 of the Embrittlement Data Base (EDB) [1] is such a compreberrsive collection of such data resulting from tbe merging of tbe Power Reactor Embrittlement Data Base (PR-EDB) [2] and the Test Reactor Embrittlement Data Base (TR-EDB) [3]. Fracture toughness data were also integrated into Version 1 of the EDB. The EDB data files are in dBASE format and can be aeeessed with a personal computer using the DOS or WINDOWS operating system, A utility program bas beeu written to investigate radiation embrittlement using this data base, The utility program is used to retrieve and select specific data, manipulate data, display data to the screen or printer, and to fit and plot Charpy impact data.

Research paper thumbnail of Mechanical Fatigue Testing of High Burnup Fuel for Transportation Applications

Research paper thumbnail of Radiation Effects on Spacecraft Structural Materials

Research is being conducted to develop an integrated technology for the prediction of aging behav... more Research is being conducted to develop an integrated technology for the prediction of aging behavior for space structural materials during service. This research will utilize state-of-the-art radiation experimental apparatus and analysis, updated codes and databases, and integrated mechanical and radiation testing techniques to investigate the suitability of numerous current and potential spacecraft structural materials. Also included are the effects on structural materials in surface modules and planetary landing craft, with or without fission power supplies. Spacecraft structural materials would also be in hostile radiation environments on the surface of the moon and planets without appreciable atmospheres and moons around planets with large intense magnetic and radiation fields (such as the Jovian moons). The effects of extreme temperature cycles in such locations compounds the effects of radiation on structural materials. This paper describes the integrated methodology in detail...

Research paper thumbnail of Development of spiral notch torsion test

Environment-Induced Cracking of Materials, 2008

Research paper thumbnail of PR-EDB: Power Reactor Embrittlement Database - Version 3

Information from radiation embrittlement research on nuclear reactor pressure vessel (RPV) steels... more Information from radiation embrittlement research on nuclear reactor pressure vessel (RPV) steels and from power-reactor surveillance reports has been gathered to assist the US Nuclear Regulatory Commission (NRC) effectively monitor current procedures and databases used by vendors, utilities, and service laboratories in the pressure vessel irradiation surveillance program. The radiation embrittlement of reactor pressure vessel materials depends on many factors, such as neutron fluence, flux, and energy spectrum, irradiation temperature, and preirradiation material history and chemical compositions. These factors must be considered to reliably predict pressure vessel embrittlement. Large amounts of data from surveillance capsules are needed to develop a generally applicable damage prediction model that can be used for industry standards and regulatory guides. Furthermore, the investigations of regulatory issues such as vessel integrity over plant life, vessel failure, and sufficiency of current codes, Standard Review Plans (SRPs), and Guides for license renewal can be greatly expedited by the use of a well-designed computerized database. The Power Reactor Embrittlement Database (PR-EDB) is such a comprehensive collection of data for U.S. operated commercial nuclear reactors. The current version of the PR-EDB lists the test results of 104 heat-affected-zone (HAZ) materials, 115 weld materials, and 141 base materials, including 103 plates, 35 forgings, and 3 correlation monitor materials that were irradiated in 321 capsules from 106 commercial power reactors. The data files are given in dBASE format and can be accessed with any personal computer using the Windows operating system. "User-friendly" utility programs have been written to investigate radiation embrittlement using this database. Utility programs allow the user to retrieve, select and manipulate specific data, display data to the screen or printer, and fit and plot Charpy impact data. The PR-EDB Version 3.0 upgrades Version 2.0. The package was developed based on the Microsoft .NET framework technology and uses Microsoft Access for backend data storage, and Microsoft Excel for plotting graphs. This software package is compatible with Windows (98 or higher) and has been built with a highly versatile user interface. PR-EDB Version 3.0 also contains an "Evaluated Residual File" utility for generating the evaluated processed files used for radiation embrittlement study.

Research paper thumbnail of The development of radiation embrittlement models for US power reactor pressure vessel steels

Journal of nuclear materials, 2007

A new approach of utilizing information fusion technique is developed to predict the radiation em... more A new approach of utilizing information fusion technique is developed to predict the radiation embrittlement of reactor pressure vessel steels. The Charpy transition temperature shift data contained in the Power Reactor Embrittlement Database is used in this study. Six parameters-Cu, Ni, P, neutron fluence, irradiation time, and irradiation temperature-are used in the embrittlement prediction models. The results indicate that this new embrittlement predictor achieved reductions of about 49.5% and 52% in the uncertainties for plate and weld data, respectively, for pressurized water reactor and boiling water reactor data, compared with the Nuclear Regulatory Commission Regulatory Guide 1.99, Rev. 2. The implications of dose-rate effect and irradiation temperature effects for the development of radiation embrittlement models are also discussed.

Research paper thumbnail of The development of radiation embrittlement models for US power reactor pressure vessel steels

Journal of nuclear materials, 2007

A new approach of utilizing information fusion technique is developed to predict the radiation em... more A new approach of utilizing information fusion technique is developed to predict the radiation embrittlement of reactor pressure vessel steels. The Charpy transition temperature shift data contained in the Power Reactor Embrittlement Database is used in this study. Six parameters-Cu, Ni, P, neutron fluence, irradiation time, and irradiation temperature-are used in the embrittlement prediction models. The results indicate that this new embrittlement predictor achieved reductions of about 49.5% and 52% in the uncertainties for plate and weld data, respectively, for pressurized water reactor and boiling water reactor data, compared with the Nuclear Regulatory Commission Regulatory Guide 1.99, Rev. 2. The implications of dose-rate effect and irradiation temperature effects for the development of radiation embrittlement models are also discussed.

Research paper thumbnail of A new approach to determine the quasi-static and dynamic fracture toughness of engineering materials

Research paper thumbnail of A new method for dynamic fracture toughness determination using torsion Hopkinson pressure bar

Research paper thumbnail of FY15 Status Report: CIRFT Testing of Spent Nuclear Fuel Rods from Boiler Water Reactor Limerick

Research paper thumbnail of Low Temperature Irradiation Embrittlement of Reactor Pressure Vessel Steels

Research paper thumbnail of FY 2014 Status Report: Quantification of CIRFT System Biases and Uncertainties Associated When Testing High Burnup Spent Nuclear Fuel

Research paper thumbnail of Investigation of Pipelines Integrity Associated With Pump Modules Vibration for Pumping Station 9 of Alyeska Pipeline Service Company

Research paper thumbnail of ARN-Atucha-I Reactor Pressure-Vessel Embrittlement

Framatome VAK accelerated surveillance data as applied to the RPV integrity study were investigat... more Framatome VAK accelerated surveillance data as applied to the RPV integrity study were investigated. The primary purpose of this report is to provide ARN with an independent interpretation of the Atucha-I surveillance data with respect to U.S. nuclear codes and standards. Another important purpose was to provide an independent evaluation of neutron dose rate and spectra effect in regard to the RPV radiation embrittlement data.

Research paper thumbnail of Development of Embrittlement Prediction Models for U.S. Power Reactors and the Impact of the Heat-Affected Zone to Thermal Annealing

Journal of ASTM International

ABSTRACT

Research paper thumbnail of A New Approach To Evaluate Fracture Toughness of Structural Materials

Research paper thumbnail of Radiation Embrittlement Prediction Models and The Impact of Irradiation Temperature

A new methodology is developed for the prediction of RPV embrittlement that utilizes a combinatio... more A new methodology is developed for the prediction of RPV embrittlement that utilizes a combination of domain models and nonlinear estimators including neural networks and nearest neighbor regressions. The Power Reactor Embrittlement Database is used in this study. The results from newly developed nearest neighbor projective fuser indicate that the combined embrittlement predictor achieved about 67.3% and 52.4% reductions in the uncertainties for General Electric Boiling Water Reactor plate and weld data compared to Regulatory Guide 1.99, Revision 2, respectively. The implications of irradiation temperature effects to the development of radiation embrittlement models are then discussed.

Research paper thumbnail of Fracture toughness evaluation for thin-shell stainless steel weldment

Theoretical and Applied Fracture Mechanics

Research paper thumbnail of High burn-up spent nuclear fuel transport reliability investigation

Nuclear Engineering and Design

Research paper thumbnail of Using Torsion Bar Testing to Determine Fracture Toughness of Ceramic Materials

Research paper thumbnail of U.S. NRC Embrittlement Data Base (EDB)

Reactor Dosimetry: Radiation Metrology and Assessment, 2001

Large amounts of data obtained from surveillance capsules and test reactor experiments are needed... more Large amounts of data obtained from surveillance capsules and test reactor experiments are needed, comprising many different materials and different irradiation conditions, to develop generally applicable damage prediction models that can be used for industry standards and regulatory guides. Version 1 of the Embrittlement Data Base (EDB) [1] is such a compreberrsive collection of such data resulting from tbe merging of tbe Power Reactor Embrittlement Data Base (PR-EDB) [2] and the Test Reactor Embrittlement Data Base (TR-EDB) [3]. Fracture toughness data were also integrated into Version 1 of the EDB. The EDB data files are in dBASE format and can be aeeessed with a personal computer using the DOS or WINDOWS operating system, A utility program bas beeu written to investigate radiation embrittlement using this data base, The utility program is used to retrieve and select specific data, manipulate data, display data to the screen or printer, and to fit and plot Charpy impact data.

Research paper thumbnail of Mechanical Fatigue Testing of High Burnup Fuel for Transportation Applications

Research paper thumbnail of Radiation Effects on Spacecraft Structural Materials

Research is being conducted to develop an integrated technology for the prediction of aging behav... more Research is being conducted to develop an integrated technology for the prediction of aging behavior for space structural materials during service. This research will utilize state-of-the-art radiation experimental apparatus and analysis, updated codes and databases, and integrated mechanical and radiation testing techniques to investigate the suitability of numerous current and potential spacecraft structural materials. Also included are the effects on structural materials in surface modules and planetary landing craft, with or without fission power supplies. Spacecraft structural materials would also be in hostile radiation environments on the surface of the moon and planets without appreciable atmospheres and moons around planets with large intense magnetic and radiation fields (such as the Jovian moons). The effects of extreme temperature cycles in such locations compounds the effects of radiation on structural materials. This paper describes the integrated methodology in detail...

Research paper thumbnail of Development of spiral notch torsion test

Environment-Induced Cracking of Materials, 2008

Research paper thumbnail of PR-EDB: Power Reactor Embrittlement Database - Version 3

Information from radiation embrittlement research on nuclear reactor pressure vessel (RPV) steels... more Information from radiation embrittlement research on nuclear reactor pressure vessel (RPV) steels and from power-reactor surveillance reports has been gathered to assist the US Nuclear Regulatory Commission (NRC) effectively monitor current procedures and databases used by vendors, utilities, and service laboratories in the pressure vessel irradiation surveillance program. The radiation embrittlement of reactor pressure vessel materials depends on many factors, such as neutron fluence, flux, and energy spectrum, irradiation temperature, and preirradiation material history and chemical compositions. These factors must be considered to reliably predict pressure vessel embrittlement. Large amounts of data from surveillance capsules are needed to develop a generally applicable damage prediction model that can be used for industry standards and regulatory guides. Furthermore, the investigations of regulatory issues such as vessel integrity over plant life, vessel failure, and sufficiency of current codes, Standard Review Plans (SRPs), and Guides for license renewal can be greatly expedited by the use of a well-designed computerized database. The Power Reactor Embrittlement Database (PR-EDB) is such a comprehensive collection of data for U.S. operated commercial nuclear reactors. The current version of the PR-EDB lists the test results of 104 heat-affected-zone (HAZ) materials, 115 weld materials, and 141 base materials, including 103 plates, 35 forgings, and 3 correlation monitor materials that were irradiated in 321 capsules from 106 commercial power reactors. The data files are given in dBASE format and can be accessed with any personal computer using the Windows operating system. "User-friendly" utility programs have been written to investigate radiation embrittlement using this database. Utility programs allow the user to retrieve, select and manipulate specific data, display data to the screen or printer, and fit and plot Charpy impact data. The PR-EDB Version 3.0 upgrades Version 2.0. The package was developed based on the Microsoft .NET framework technology and uses Microsoft Access for backend data storage, and Microsoft Excel for plotting graphs. This software package is compatible with Windows (98 or higher) and has been built with a highly versatile user interface. PR-EDB Version 3.0 also contains an "Evaluated Residual File" utility for generating the evaluated processed files used for radiation embrittlement study.

Research paper thumbnail of The development of radiation embrittlement models for US power reactor pressure vessel steels

Journal of nuclear materials, 2007

A new approach of utilizing information fusion technique is developed to predict the radiation em... more A new approach of utilizing information fusion technique is developed to predict the radiation embrittlement of reactor pressure vessel steels. The Charpy transition temperature shift data contained in the Power Reactor Embrittlement Database is used in this study. Six parameters-Cu, Ni, P, neutron fluence, irradiation time, and irradiation temperature-are used in the embrittlement prediction models. The results indicate that this new embrittlement predictor achieved reductions of about 49.5% and 52% in the uncertainties for plate and weld data, respectively, for pressurized water reactor and boiling water reactor data, compared with the Nuclear Regulatory Commission Regulatory Guide 1.99, Rev. 2. The implications of dose-rate effect and irradiation temperature effects for the development of radiation embrittlement models are also discussed.

Research paper thumbnail of The development of radiation embrittlement models for US power reactor pressure vessel steels

Journal of nuclear materials, 2007

A new approach of utilizing information fusion technique is developed to predict the radiation em... more A new approach of utilizing information fusion technique is developed to predict the radiation embrittlement of reactor pressure vessel steels. The Charpy transition temperature shift data contained in the Power Reactor Embrittlement Database is used in this study. Six parameters-Cu, Ni, P, neutron fluence, irradiation time, and irradiation temperature-are used in the embrittlement prediction models. The results indicate that this new embrittlement predictor achieved reductions of about 49.5% and 52% in the uncertainties for plate and weld data, respectively, for pressurized water reactor and boiling water reactor data, compared with the Nuclear Regulatory Commission Regulatory Guide 1.99, Rev. 2. The implications of dose-rate effect and irradiation temperature effects for the development of radiation embrittlement models are also discussed.

Research paper thumbnail of A new approach to determine the quasi-static and dynamic fracture toughness of engineering materials

Research paper thumbnail of A new method for dynamic fracture toughness determination using torsion Hopkinson pressure bar

Research paper thumbnail of FY15 Status Report: CIRFT Testing of Spent Nuclear Fuel Rods from Boiler Water Reactor Limerick

Research paper thumbnail of Low Temperature Irradiation Embrittlement of Reactor Pressure Vessel Steels

Research paper thumbnail of FY 2014 Status Report: Quantification of CIRFT System Biases and Uncertainties Associated When Testing High Burnup Spent Nuclear Fuel

Research paper thumbnail of Investigation of Pipelines Integrity Associated With Pump Modules Vibration for Pumping Station 9 of Alyeska Pipeline Service Company

Research paper thumbnail of ARN-Atucha-I Reactor Pressure-Vessel Embrittlement

Framatome VAK accelerated surveillance data as applied to the RPV integrity study were investigat... more Framatome VAK accelerated surveillance data as applied to the RPV integrity study were investigated. The primary purpose of this report is to provide ARN with an independent interpretation of the Atucha-I surveillance data with respect to U.S. nuclear codes and standards. Another important purpose was to provide an independent evaluation of neutron dose rate and spectra effect in regard to the RPV radiation embrittlement data.

Research paper thumbnail of Development of Embrittlement Prediction Models for U.S. Power Reactors and the Impact of the Heat-Affected Zone to Thermal Annealing

Journal of ASTM International

ABSTRACT

Research paper thumbnail of A New Approach To Evaluate Fracture Toughness of Structural Materials

Research paper thumbnail of Radiation Embrittlement Prediction Models and The Impact of Irradiation Temperature

A new methodology is developed for the prediction of RPV embrittlement that utilizes a combinatio... more A new methodology is developed for the prediction of RPV embrittlement that utilizes a combination of domain models and nonlinear estimators including neural networks and nearest neighbor regressions. The Power Reactor Embrittlement Database is used in this study. The results from newly developed nearest neighbor projective fuser indicate that the combined embrittlement predictor achieved about 67.3% and 52.4% reductions in the uncertainties for General Electric Boiling Water Reactor plate and weld data compared to Regulatory Guide 1.99, Revision 2, respectively. The implications of irradiation temperature effects to the development of radiation embrittlement models are then discussed.