The development of radiation embrittlement models for U.S. power reactor pressure vessel steels

J. A. Wang; N. S.V. Rao; S. Konduri

doi:10.1115/PVP2006-ICPVT-11-94022

The development of radiation embrittlement models for U.S. power reactor pressure vessel steels

J. A. Wang
, N. S.V. Rao
, S. Konduri

Autonomous and Complex Systems

Research output: Chapter in Book/Report/Conference proceeding › Conference contribution › peer-review

Abstract

The information fusion technique is used to develop radiation embrittlement prediction models for reactor pressure vessel (RPV) steels from U.S. power reactors, including boiling water reactors and pressurized water reactors. The Charpy transition temperature-shift data is used as the primary index of 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 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.

Original language	English
Title of host publication	Proceedings of 2006 ASME Pressure Vessels and Piping Division Conference - ASME PVP2006/ICPVT-11 Conference - Pressure Vessel Technologies for the Global Community
Publisher	American Society of Mechanical Engineers (ASME)
ISBN (Print)	0791837823, 9780791837825
DOIs	https://doi.org/10.1115/PVP2006-ICPVT-11-94022
State	Published - 2006
Event	ASME PVP2006/ICPVT-11 Conference - Vancouver, BC, Canada Duration: Jul 23 2006 → Jul 27 2006

Publication series

Name	American Society of Mechanical Engineers, Pressure Vessels and Piping Division (Publication) PVP
Volume	2006
ISSN (Print)	0277-027X

Conference

Conference	ASME PVP2006/ICPVT-11 Conference
Country/Territory	Canada
City	Vancouver, BC
Period	07/23/06 → 07/27/06

Funding

This research is sponsored by the Laboratory Directed Research and Development Seed Money Program and the Radiation Safety Information Computational Center of Oak Ridge National Laboratory, and by the Materials Science and Engineering Division, Office of Basic Energy Sciences, of the US Department of Energy, under contract DE-AC05-00OR22725 with UT-Battelle, LLC.

Keywords

Embrittlement prediction models
Information fusion
Power reactor
Radiation embrittlement

Access to Document

10.1115/PVP2006-ICPVT-11-94022

Cite this

Wang, J. A., Rao, N. S. V., & Konduri, S. (2006). The development of radiation embrittlement models for U.S. power reactor pressure vessel steels. In Proceedings of 2006 ASME Pressure Vessels and Piping Division Conference - ASME PVP2006/ICPVT-11 Conference - Pressure Vessel Technologies for the Global Community (American Society of Mechanical Engineers, Pressure Vessels and Piping Division (Publication) PVP; Vol. 2006). American Society of Mechanical Engineers (ASME). https://doi.org/10.1115/PVP2006-ICPVT-11-94022

Wang, J. A. ; Rao, N. S.V. ; Konduri, S. / The development of radiation embrittlement models for U.S. power reactor pressure vessel steels. Proceedings of 2006 ASME Pressure Vessels and Piping Division Conference - ASME PVP2006/ICPVT-11 Conference - Pressure Vessel Technologies for the Global Community. American Society of Mechanical Engineers (ASME), 2006. (American Society of Mechanical Engineers, Pressure Vessels and Piping Division (Publication) PVP).

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title = "The development of radiation embrittlement models for U.S. power reactor pressure vessel steels",

abstract = "The information fusion technique is used to develop radiation embrittlement prediction models for reactor pressure vessel (RPV) steels from U.S. power reactors, including boiling water reactors and pressurized water reactors. The Charpy transition temperature-shift data is used as the primary index of 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 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.",

keywords = "Embrittlement prediction models, Information fusion, Power reactor, Radiation embrittlement",

author = "Wang, \{J. A.\} and Rao, \{N. S.V.\} and S. Konduri",

year = "2006",

doi = "10.1115/PVP2006-ICPVT-11-94022",

language = "English",

isbn = "0791837823",

series = "American Society of Mechanical Engineers, Pressure Vessels and Piping Division (Publication) PVP",

publisher = "American Society of Mechanical Engineers (ASME)",

booktitle = "Proceedings of 2006 ASME Pressure Vessels and Piping Division Conference - ASME PVP2006/ICPVT-11 Conference - Pressure Vessel Technologies for the Global Community",

note = "ASME PVP2006/ICPVT-11 Conference ; Conference date: 23-07-2006 Through 27-07-2006",

}

Wang, JA, Rao, NSV & Konduri, S 2006, The development of radiation embrittlement models for U.S. power reactor pressure vessel steels. in Proceedings of 2006 ASME Pressure Vessels and Piping Division Conference - ASME PVP2006/ICPVT-11 Conference - Pressure Vessel Technologies for the Global Community. American Society of Mechanical Engineers, Pressure Vessels and Piping Division (Publication) PVP, vol. 2006, American Society of Mechanical Engineers (ASME), ASME PVP2006/ICPVT-11 Conference, Vancouver, BC, Canada, 07/23/06. https://doi.org/10.1115/PVP2006-ICPVT-11-94022

The development of radiation embrittlement models for U.S. power reactor pressure vessel steels. / Wang, J. A.; Rao, N. S.V.; Konduri, S.
Proceedings of 2006 ASME Pressure Vessels and Piping Division Conference - ASME PVP2006/ICPVT-11 Conference - Pressure Vessel Technologies for the Global Community. American Society of Mechanical Engineers (ASME), 2006. (American Society of Mechanical Engineers, Pressure Vessels and Piping Division (Publication) PVP; Vol. 2006).

Research output: Chapter in Book/Report/Conference proceeding › Conference contribution › peer-review

TY - GEN

T1 - The development of radiation embrittlement models for U.S. power reactor pressure vessel steels

AU - Wang, J. A.

AU - Rao, N. S.V.

AU - Konduri, S.

PY - 2006

Y1 - 2006

N2 - The information fusion technique is used to develop radiation embrittlement prediction models for reactor pressure vessel (RPV) steels from U.S. power reactors, including boiling water reactors and pressurized water reactors. The Charpy transition temperature-shift data is used as the primary index of 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 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.

AB - The information fusion technique is used to develop radiation embrittlement prediction models for reactor pressure vessel (RPV) steels from U.S. power reactors, including boiling water reactors and pressurized water reactors. The Charpy transition temperature-shift data is used as the primary index of 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 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.

KW - Embrittlement prediction models

KW - Information fusion

KW - Power reactor

KW - Radiation embrittlement

UR - https://www.scopus.com/pages/publications/33751315096

U2 - 10.1115/PVP2006-ICPVT-11-94022

DO - 10.1115/PVP2006-ICPVT-11-94022

M3 - Conference contribution

AN - SCOPUS:33751315096

SN - 0791837823

SN - 9780791837825

T3 - American Society of Mechanical Engineers, Pressure Vessels and Piping Division (Publication) PVP

BT - Proceedings of 2006 ASME Pressure Vessels and Piping Division Conference - ASME PVP2006/ICPVT-11 Conference - Pressure Vessel Technologies for the Global Community

PB - American Society of Mechanical Engineers (ASME)

T2 - ASME PVP2006/ICPVT-11 Conference

Y2 - 23 July 2006 through 27 July 2006

ER -

Wang JA, Rao NSV, Konduri S. The development of radiation embrittlement models for U.S. power reactor pressure vessel steels. In Proceedings of 2006 ASME Pressure Vessels and Piping Division Conference - ASME PVP2006/ICPVT-11 Conference - Pressure Vessel Technologies for the Global Community. American Society of Mechanical Engineers (ASME). 2006. (American Society of Mechanical Engineers, Pressure Vessels and Piping Division (Publication) PVP). doi: 10.1115/PVP2006-ICPVT-11-94022

The development of radiation embrittlement models for U.S. power reactor pressure vessel steels

Abstract

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Keywords

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