A new approach that utilizes the information fusion technique was developed to predict the radiation embrittlement of reactor pressure vessel (RPV) steels. The Charpy transition temperature-shift data is used as the primary index of the RPV radiation embrittlement 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 about 66% and 53% reductions, respectively, in the uncertainties for the update General Electric (GE) Boiling Water Reactor (BWR) plate and weld data compared to the Nuclear Regulatory Commission (NRC) Regulatory Guide 1.99, Rev. 2 (RG1.99/R2). The implications of irradiation temperature effects for the development of radiation embrittlement models are also discussed.
Skip Nav Destination
e-mail: wangja@ornl.gov
Article navigation
February 2005
Article
Information Fusion Technique for Evaluating Radiation Embrittlement of Reactor Pressure Vessel Steels
J. A. Wang,
e-mail: wangja@ornl.gov
J. A. Wang
Oak Ridge National Laboratory, 1 Bethel Valley Road, Oak Ridge, TN 37831, Telephone: 865-574-2274
Search for other works by this author on:
S. Konduri,
S. Konduri
Oak Ridge National Laboratory, 1 Bethel Valley Road, Oak Ridge, TN 37831, Telephone: 865-574-2274
Search for other works by this author on:
N. S. V. Rao
N. S. V. Rao
Oak Ridge National Laboratory, 1 Bethel Valley Road, Oak Ridge, TN 37831, Telephone: 865-574-2274
Search for other works by this author on:
J. A. Wang
Oak Ridge National Laboratory, 1 Bethel Valley Road, Oak Ridge, TN 37831, Telephone: 865-574-2274
e-mail: wangja@ornl.gov
S. Konduri
Oak Ridge National Laboratory, 1 Bethel Valley Road, Oak Ridge, TN 37831, Telephone: 865-574-2274
N. S. V. Rao
Oak Ridge National Laboratory, 1 Bethel Valley Road, Oak Ridge, TN 37831, Telephone: 865-574-2274
Paper presented at the 2004 ASME Pressure Vessels and Piping Division Conference (PVP2004), July 25–29, 2004, San Diego, California, USA. Contributed by the Pressure Vessels and Piping Division for publication in the JOURNAL OF PRESSURE VESSEL TECHNOLOGY. Manuscript received by the PVP Division September 8, 2004; revision received November 23, 2004. Review conducted by: S. Zamrik.
J. Pressure Vessel Technol. Feb 2005, 127(1): 98-104 (7 pages)
Published Online: March 15, 2005
Article history
Received:
September 8, 2004
Revised:
November 23, 2004
Online:
March 15, 2005
Citation
Wang, J. A., Konduri , S., and Rao , N. S. V. (March 15, 2005). "Information Fusion Technique for Evaluating Radiation Embrittlement of Reactor Pressure Vessel Steels." ASME. J. Pressure Vessel Technol. February 2005; 127(1): 98–104. https://doi.org/10.1115/1.1858926
Download citation file:
Get Email Alerts
Cited By
The Behavior of Elbow Elements at Pure Bending Applications Compared to Beam and Shell Element Models
J. Pressure Vessel Technol (February 2025)
Related Articles
Characteristics of the New Embrittlement Correlation Method for the Japanese Reactor Pressure Vessel Steels
J. Eng. Gas Turbines Power (October,2010)
Modeling of Irradiation Embrittlement of Reactor Pressure Vessel Steels
J. Eng. Mater. Technol (January,2000)
Guest Editorial
J. Pressure Vessel Technol (February,2004)
Radiation and Temper Embrittlement Processes in Advanced Reactor Weld Metals
J. Eng. Ind (August,1972)
Related Chapters
Hydrogen Uptake and Embrittlement Susceptibility of Ferrite-Pearlite Pipeline Steels
International Hydrogen Conference (IHC 2016): Materials Performance in Hydrogen Environments
Lessons Learned: NRC Experience
Continuing and Changing Priorities of the ASME Boiler & Pressure Vessel Codes and Standards
Prediction of Reference Transition Temperature Increase Due to Neutron Irradiation Exposure
Radiation Embrittlement of Nuclear Reactor Pressure Vessel Steels: An International Review (Second Volume)