347
Views
0
CrossRef citations to date
0
Altmetric
Article

Statistical arguments towards the development of an advanced embrittlement correlation method for reactor pressure vessel materials

&
Pages 312-322 | Received 19 Jul 2019, Accepted 25 Sep 2019, Published online: 30 Oct 2019

References

  • Was GS. Fundamentals of radiation materials science: metals and alloys. New York: Springer; 2007.
  • Odette GR, Lucas GE. Embrittlement of nuclear reactor pressure vessels. JOM: J Miner Met Mater Soc 2001 Jan;53(7):18–22.
  • Phythian WJ, English CA. Microstructural evolution in reactor pressure vessel steels. J Nucl Mater. 1993 Oct;205:162–177.
  • Fukuya K. Current understanding of radiation-induced degradation in light water reactor structural materials. J Nucl Sci Technol. 2013 Mar;50(3):213–254.
  • Ishino S, Sekimura N, Suzuki M, et al. Present status of radiation-damage mechanism study on reactor pressure vessels based on irradiation correlation concept. J At Energy Soc Jpn. 1994 May;36:396–404. Japanese.
  • Mishima Y, Ishino S, Ishikawa M, et al. PTS integrity study in Japan. Int J Pres Ves Pip. 1994;58(1):91–101.
  • Ruan X, Nakasuji T, Morishita K. An investigation of the structural integrity of a reactor pressure vessel using 3D-CFD and FEM based probabilistic pressurized thermal shock analysis for optimizing maintenance strategy. J Pressure Vessel Technol. 2018 Oct;140(5):051302-051302-10.
  • Tipping PG, editor. Understanding and mitigating ageing in nuclear power plants: materials and Operational Aspects of Plant Life Management (PLIM). Oxford: Woodhead publishing in energy; 2010.
  • US Nuclear Regulatory Commission. Rules and regulations title 10 code of federal regulations part 50 fracture toughness requirement. Washington (DC): US Government Printing Office; 1986.
  • U.S. Nuclear Regulatory Commission. regulatory guide 1.99-rev.2: radiation embrittlement to reactor pressure vessel materials. Washington (DC): US Government Printing Office; 1988.
  • Eason ED, Wright JE, Odette GR. Improved embrittlement correlations for reactor pressure vessel steels. Washington DC: US Government Printing Office; 1998 Nov. (US Nuclear Regulatory Commission Report No. NUREG/CR-6551).
  • Eason ED, Odette GR, Nanstad RK, et al. Physically based correlation of irradiation-induced transition temperature shifts for RPV steels. Washington (DC): US Government Printing Office; 2007. (US nuclear regulatory commission report No. ORNL-TM-2006/530).
  • American Society for Testing and Materials. Standard guide for predicting radiation-induced transition temperature shift for reactor vessel materials, E706 (IIF): ASTM E900-02. West Conshohocken (PA): American Society for Testing and Materials; 2002.
  • Japan Electric Association. Method of surveillance tests for structural materials of nuclear reactors: JEAC 4201-2007. Tokyo (Japan): Japan Electric Association; 2007 Dec. Japanese
  • Japan Electric Association. Method of surveillance tests for structural materials of nuclear reactors: JEAC 4201-2007 [2010 addendum]. Tokyo (Japan): Japan Electric Association; 2010 Jul. Japanese
  • Japan Electric Association. Method of surveillance tests for structural materials of nuclear reactors: JEAC 4201-2007 [2013 addendum]. Tokyo (Japan): Japan Electric Association; 2013 Sep. Japanese
  • Soneda N, Nakashima K, Nishida K, et al. Modification of embrittlement correlation method of reactor pressure vessel steels – development of neutron irradiation embrittlement correlation of reactor pressure vessel materials of light water reactors: CRIEPI report Q06019. Tokyo (Japan): Central Research Institute of Electric Power Industry; 2007 Apr. Japanese
  • Soneda N, Nakashima K, Nishida K, et al. Modification of embrittlement correlation method of reactor pressure vessel steels – calibration to the surveillance test data at high fluence –: CRIEPI report Q12007. Tokyo (Japan): Central Research Institute of Electric Power Industry; 2013 Mar. Japanese
  • Soneda N, Dohi K, Nomoto A, et al. Embrittlement correlation method for the Japanese reactor pressure vessel materials: JAI102127. J ASTM Int. 2010 Feb;7(3):64–93.
  • Soneda N, Dohi K, Nishida K, et al. Microstructural characterization of RPV materials irradiated to high fluences at high flux: JAI102128. J ASTM Int. 2009 Aug;6(7):129–152.
  • Soneda N, Nakashima K, Nishida K, et al. High fluence surveillance data and recalibration of RPV embrittlement correlation method in Japan: PVP2013-98076. In: Barannyk O, Karri S, Oshkai P, editors. Proceedings of the ASME 2013 pressure vessels and piping conference; 2013 Jul 14–18; Paris (France). New York: American Society of Mechanical Engineers; 2013. p. 1–12.
  • Nuclear Regulation Authority. Technical evaluation report on JEAC4201-2007 [2013 addendum]: method of surveillance tests for structural materials of nuclear reactors. [ updated 2015 Oct 7; cited 2019 Jul 19]:[68p.]. Available from: http://www.nsr.go.jp/data/000125554.pdf. Japanese.
  • Kyushu Electric Power CO. Inc. On the integrity of reactor pressure vessels against irradiation embrittlement. [ updated 2012 Dec 21; cited 2019 Jul 19]:[10p.]. Available from: http://www.kyuden.co.jp/library/pdf/nuclear/nuclear_irradiation121221.pdf. Japanese.
  • Kansai Electric Power Co. Inc. Units 1 and 2 of Takahama power station, Evaluation of degradation (neutron irradiation embrittlement of reactor vessel), supplementary explanation documents. [ updated 2016 Jun; cited 2018 Jul]. Available from: http://www.nsr.go.jp/data/000143515.pdf. Japanese.
  • Shikoku Electric Power Co. Inc. On the result of surveillance tests of reactor pressure vessels in unit 1 of Ikata power station. [ updated 2013 Jul; cited 2019 Jul]:[5p.]. Available from: https://www.yonden.co.jp/press/re1307/data/pr007-01.pdf. Japanese.
  • Ramachandran KM, Tsokos CP. Mathematical statistics with applications. 1st ed. Cambridge (MA): Academic Press; 2009.
  • Ayyub BM, McCuen RH. Probability, statistics, and reliability for engineers and scientists. 2nd ed. Boca Raton (FL): CRC press; 2003.
  • Stapleton JH. Models for probability and statistical inference: theory and applications. Hoboken (NJ): Wiley; 2007.
  • Soneda N. Development of RPV embrittlement correlation method: annual report 2005 nuclear technology research laboratory. Tokyo (Japan): Central Research Institute of Electric Power Industry; 2005 Oct [ updated 2005 Oct; cited 2019 Jul]:[2p.]. Available from: https://criepi.denken.or.jp/jp/nuclear/contents/result/annual2005/5.pdf. Japanese. For more detail see also, Soneda N, English C, Server W. Use of an offset in assessing radiation embrittlement data and predictive models: PVP2006-ICPVT11-93369. In: Todd JA, Cory JF, Zamrik SY, et al., editors. Proceedings of the ASME 2006 Pressure Vessels and Piping Conference; 2006 Jul 23–27; Vancouver (Canada). New York: American Society of Mechanical Engineers; 2006. p. 351–357.
  • Nuclear and Industrial Safety Agency (NISA). 5th opinion hearing on technical assessment of aging management of nuclear power plants document-2: on neutron irradiation embrittlement of reactor pressure vessel. [ updated 2012 Jan; cited 2019 Jul]:[11p.]. Available from: http://dl.ndl.go.jp/view/download/digidepo_6011694_po_5-2.pdf?contentNo=6&alternativeNo= Japanese.
  • Lee JC, McCormick NJ. Risk and safety analysis of nuclear systems. Hoboken (NJ): Wiley; 2011.
  • Yamamoto Y, Morishita K. Development of methodology to optimize management of failed fuels in light water reactors. J Nucl Sci Technol. 2015 May;52(5):709–716.

Reprints and Corporate Permissions

Please note: Selecting permissions does not provide access to the full text of the article, please see our help page How do I view content?

To request a reprint or corporate permissions for this article, please click on the relevant link below:

Academic Permissions

Please note: Selecting permissions does not provide access to the full text of the article, please see our help page How do I view content?

Obtain permissions instantly via Rightslink by clicking on the button below:

If you are unable to obtain permissions via Rightslink, please complete and submit this Permissions form. For more information, please visit our Permissions help page.