反应堆压力容器钢辐照硬化脆化的中子注量率效应

王荣山, 徐超亮, 黄平, 刘向兵

科技导报 ›› 2014, Vol. 32 ›› Issue (31) : 80-84.

PDF(1547 KB)
PDF(1547 KB)
科技导报 ›› 2014, Vol. 32 ›› Issue (31) : 80-84. DOI: 10.3981/j.issn.1000-7857.2014.31.012
综述文章

反应堆压力容器钢辐照硬化脆化的中子注量率效应

作者信息 -
苏州热工研究院, 苏州 215004
作者简介:
王荣山,博士研究生,研究方向为核电站延寿与关键部件老化管理,电子邮箱:cntsail@126.com

Summaries of Neutron Fluence Rate Effects on Hardening and Embrittlement of Nuclear Reactor Pressure Vessel Steels

Author information -
Suzhou Nuclear Power Research Institute, Suzhou 215004, China

摘要

针对中子注量率对核电站反应堆压力容器(RPV)钢辐照硬化脆化的影响,总结了不同铜含量RPV 钢的辐照硬化脆化的中子注量率效应.结果表明,在低铜(Cu≤0.08%)和高铜(Cu>0.08%)RPV 钢中,中子注量率对辐照硬化脆化有不同的作用结果.在中子注量率≤1×1012 n·cm-2·s-1(E>1 MeV)的条件下,中子注量率对低铜RPV 钢辐照硬化脆化无明显影响,在>1×1012n·cm-2·s-1(E>1 MeV)的条件下,尚无确定结论;高铜RPV 钢辐照至富铜团簇硬化平台后,注量率对硬化脆化无影响,而达到辐照硬化平台之前,注量率对辐照硬化脆化有不同影响.

Abstract

The effect of neutron fluence rate on hardening and embrittlement of nuclear reactor pressure vessel (RPV) is summarized. It is indicated that the effect of neutron fluence rate on hardening and embrittlement has different influences on low-Cu (Cu≤0.08%) and high-Cu (Cu>0.08%) RPV steels. The irradiation hardening and embrittlement have no relationship with neutron fluence rate up to 1×1012 n·cm-2·s-1 (E>1 MeV) in low-Cu RPV steel, but do not show definite connection if the fluence rate >1×1012 n·cm-2·s-1 (E>1 MeV). The hardening and embrittlement have nothing to do with the fluence rate if the plateau in Cu-related hardening is reached. The behavior of Cu-containing steels is more complex at the pre-plateau fluence.

关键词

RPV 钢 / 辐照硬化脆化 / 中子注量率

Key words

RPV steel / irradiation hardening and embrittlement / neutron fluence rate

引用本文

导出引用
王荣山, 徐超亮, 黄平, 刘向兵. 反应堆压力容器钢辐照硬化脆化的中子注量率效应[J]. 科技导报, 2014, 32(31): 80-84 https://doi.org/10.3981/j.issn.1000-7857.2014.31.012
WANG Rongshan, XU Chaoliang, HUANG Ping, LIU Xiangbing. Summaries of Neutron Fluence Rate Effects on Hardening and Embrittlement of Nuclear Reactor Pressure Vessel Steels[J]. Science & Technology Review, 2014, 32(31): 80-84 https://doi.org/10.3981/j.issn.1000-7857.2014.31.012
中图分类号: TL351+.6   

参考文献

[1] Odette G R, Lucas G E. Recent progress in understanding reactor pressure vessel steel embrittlement[J]. Radiation Effects and Defects in Solids, 1998, 44(1-4): 189-231.
[2] Meslin E, Radiguet B, Pareige P, et al. Kinetic of solute clustering in neutron irradiated ferritic model alloys and a french pressure vessel steel investigated by atom probe tomography[J]. Journal of Nuclear Materials, 2010, 399(2/3): 137-145.
[3] Nikolaeva A V, Nikolaev Y A, Kryukov A M. The contribution of grain boundary effects to low-alloy steel irradiation embrittlement[J]. Journal of Nuclear Materials, 1995, 218: 85-93.
[4] Hawthorne J R, Steele L E. Metallurgical variables as possible factors controlling irradiation response of structural steel[C]. Effects of Radiation on Structural Metals, Atlantic, June 26-July 1,1966.
[5] Miller M K, Burke M G. An atom probe field ion microscopy study of neutron-irradiated pressure vessel steels[J]. Journal of Nuclear Materials, 1992, 195: 68-82.
[6] Kocik J, Keilova E, Cizek J, et al. TEM and PAS study of neutron irradiated VVER- type RPV steels[J]. Journal of Nuclear Materials, 2002, 303: 52-64.
[7] Lee T H, Kim Y O, Kim S J. Crystallographic model for Bcc-to-9R martensitic transformation of Cu precipitates in ferritic steel[J]. Philosophical Magazine, 2007, 87(2): 209-224.
[8] Monzen R, Iguchi M, Jenkins M L. Structural changes of 9R copper precipitates in an aged Fe-Cu alloy[J]. Philosophical Magazine Letters, 2000, 80: 137-148.
[9] Glade S C, Wirth B D, Odette G R, et al. Positron annihilation spectroscopy and small angle neutron scattering characterization of nanostructural features in high-nickel model reactor pressure vessel steels[J]. Journal of Nuclear Materials, 2006, 351(1-3): 197-208.
[10] Takeuchi T, Kuramoto A, Kameda J, et al. Effects of chemical composition and dose on microstructure evolution and hardening of neutronirradiated reactor pressure vessel steels[J]. Journal of Nuclear Materials, 2010, 402(2/3): 93-101.
[11] Carter R G, Soneda N, Dohi K, et al. Microstructural characterization of irradiation- induced Cu- enriched clusters in reactor pressure vessel steels[J]. Journal of Nuclear Materials, 2001, 298(3): 211-224.
[12] Bergner F, Ulbricht A, Viehrig H W. Acceleration of irradiation hardening of low- copper reactor pressure vessel steel observed by means of SANS and tensile testing[J]. Philosophical Magazine Letters, 2009, 89: 795-805.
[13] Chaouadi R, Gérard R. Copper precipitate hardening of irradiated RPV materials and implications on the superposition law and re-irradiation kinetics[J]. Journal of Nuclear Materials, 2005, 345: 65-74.
[14] Hawthorne J R. Irradiation embrittlement[J]. Treatise on Materials Science & Technology, 1983, 25: 461-524.
[15] Serpan C Z. Damage-function analysis of neutron induced embrittlement in A302- B steel at 550 F[C]. Effects of Radiation on Substructure and Mechanical Properties of Metals and Alloys, Los Angeles, USA, June 26-28, 1972.
[16] Haggag F M. Effects of irradiation temperature on embrittlement of nuclear pressure vessel steels[C]. Effects of Radiation on Materials: 16th International Symposium, Aurora CO, USA, June 23-25, 1992.
[17] Kupca L, Beno P. Analysis of the results from the surveillance specimen program for reactor pressure vessels on nuclear power plant V- 2 in Jaslovske Bohunice[C]. Radiation Embrittlement of Nuclear Reactor Pressure Vessel Steels: An International Review (4th Volume), Balatonfüred, Hungary, September 26-29, 1990.
[18] Odette G R, Mader E V, Lucas G E, et al. The effect of flux on the irradiation hardening of pressure vessel steels[C]. Effects of Radiation on Materials: Sixteenth International Symposium, Aurora CO, USA, June 23-25, 1992.
[19] Odette G R, Yamamoto T, Klingensmith D, et al. On the effect of dose rate on irradiation hardening of RPV steels[J]. Philosophical Magazine, 2005, 85: 779-797.
[20] Dohi K, Soneda N, Onchi T, et al. Dose rate effect in low copper steels irradiated in FNR[C]. Workshop on Dose Rate Effects in Reactor Pressure Vessel Materials, Squaw Creek, Canada, November, 2001.
[21] Ryuta Kasada, Takeshi Kudo, Akihiko Kimura, et al. Effects of neutron dose, dose rate, and irradiation temperature on the irradiation embrittlement of a low-copper reactor pressure vessel steel[C]. Effects of Radiation on Materials: 22nd Symposium, Boston Massachusetts, USA, June 8-10, 2004.
[22] Electric Power Research Institute (EPRI). Review of dose rate effects on RPV embrittlement[R]. California, USA, EPRI, 2002.
[23] Suzuki M, Onizawa K, Kizaki M. Effects of neutron flux and irradiation temperature on irradiation embrittlement of A533B steels[J]. Effects of Radiation on Materials: 17th International Symposium, Idaho Sun Valley, USA, June 20-23, 1994.
[24] Odette G R. Microstructure of irradiated materials[J]. Materials Research Society Symposia Proceedings, 1995, 373: 137-146.
[25] 杨文斗. 反应堆材料学[M]. 北京: 原子能出版社, 2000: 173-174. Yang Wendou. Nuclear materials[M]. Beijing: Atomic Energy Press, 2000: 173-174.
[26] International Atomic Energy Agency (IAEA). Integrity of reactor pressure vessels in nuclear power plants: assessment of irradiation embrittlement effects in reactor pressure vessel steels[R]. Vienna: IAEA, 2009.
[27] Langer R, Bartsch R, Foehl J. Irradiation results for different reactors[C]. Workshop on Dose Rate Effects in Reactor Pressure Vessel Materials, Squaw Creek, Canada, November, 2001.
[28] Williams T J, Phythian W J. Electron microscopy and SANS study of the effect of irradiation dose and dose rate on copper precipitation in low alloy steel submerged- arc welds[C]. Effects of Radiation on Materials: 17th International Symposium, Idaho Sun Valley, USA, June 20-23, 1994.
[29] Williams T, Ellis D, Connell W O. Dose rate effects in high and low nickel welds[C]. Workshop on Dose Rate Effects in Reactor Pressure Vessel Materials, Squaw Creek, Canada, November, 2001.

基金

国家高技术研究发展计划(863计划)项目(2012AA050901);苏州市科技发展计划项目(SYG201254)
PDF(1547 KB)

Accesses

Citation

Detail

段落导航
相关文章

/