Reactor pressure vessel embrittlement of NPP borssele: Design lifetime and lifetime extension

被引:5
|
作者
Blom, F. J. [1 ]
机构
[1] NRG, NL-1755 ZG Petten, Netherlands
关键词
D O I
10.1016/j.nucengdes.2007.02.008
中图分类号
TL [原子能技术]; O571 [原子核物理学];
学科分类号
0827 ; 082701 ;
摘要
Embrittlement of the reactor pressure vessel of the Borssele nuclear power plant has been investigated taking account of the design lifetime of 40 years and considering 20 years subsequent lifetime extension. The paper presents the current licensing status based on considerations of material test data and of US nuclear regulatory standards. Embrittlement status is also evaluated against German and French nuclear safety standards. Results from previous fracture toughness and Charpy tests are investigated by means of the Master curve toughness transition approach. Finally, state of the art insights are investigated by means of literature research. Regarding the embrittlement status of the reactor pressure vessel of Borssele nuclear power plant it is concluded that there is a profound basis for the current license up to the original end of the design life in 2013. The embrittlement temperature changes only slightly with respect to the acceptance criterion adopted postulating further operation up to 2033. Continued safe operation and further lifetime extension are therefore not restricted by reactor pressure vessel embrittlement. (C) 2007 Elsevier B.V. All rights reserved.
引用
收藏
页码:2098 / 2104
页数:7
相关论文
共 50 条
  • [31] Composition and magnetic character of nanometre-size Cu precipitates in reactor pressure vessel steels: implications for nuclear power plant lifetime extension
    Asoka-Kumar, P
    Wirth, BD
    Sterne, PA
    Howell, RH
    Odette, GR
    PHILOSOPHICAL MAGAZINE LETTERS, 2002, 82 (11) : 609 - 615
  • [32] VVER pressure vessel neutron dosimetry and lifetime prediction
    Adamchik, SA
    Grivizirsky, VA
    Gordon, BG
    Kaliberda, IV
    Khrennikov, NN
    Borodkin, GI
    REACTOR DOSIMETRY IN THE 21ST CENTURY, 2003, : 10 - 17
  • [33] NEUTRON IRRADIATION EMBRITTLEMENT OF REACTOR PRESSURE VESSEL STEELS.
    Steele, L.E.
    International Atomic Energy Agency, Technical Report Series, 1975, (163):
  • [34] Embrittlement recovery due to annealing of reactor pressure vessel steels
    Eason, ED
    Wright, JE
    Nelson, EE
    Odette, GR
    Mader, EV
    NUCLEAR ENGINEERING AND DESIGN, 1998, 179 (03) : 257 - 265
  • [35] Mechanisms and modeling of irradiation embrittlement of reactor pressure vessel steels
    Murakami, Sumio
    Miyazaki, Atsushi
    Tsugihashi, Kazuki
    Mizuno, Mamoru
    Jincho, Morio
    Suzuki, Tetsuya
    Zairyo/Journal of the Society of Materials Science, Japan, 1998, 47 (11): : 1112 - 1118
  • [36] Irradiation Embrittlement Behavior and Prediction of Domestic Reactor Pressure Vessel
    Lin H.
    Zhong W.
    Tong Z.
    Ning G.
    Zhang C.
    Yang W.
    Yuanzineng Kexue Jishu/Atomic Energy Science and Technology, 2021, 55 (07): : 1170 - 1176
  • [37] Miniaturized Charpy test for reactor pressure vessel embrittlement characterization
    Manahan, MP
    EFFECTS OF RADIATION ON MATERIALS: 18TH INTERNATIONAL SYMPOSIUM, 1999, 1325 : 191 - 203
  • [38] Radiation annealing of radiation embrittlement of the reactor pressure vessel steel
    Krasikov, E.
    Nikolaenko, V.
    INTERNATIONAL SCIENTIFIC CONFERENCE ON RADIATION-THERMAL EFFECTS AND PROCESSES IN INORGANIC MATERIALS 2015 (RTEP2015), 2016, 110
  • [39] NEUTRON IRRADIATION EMBRITTLEMENT OF REACTOR PRESSURE-VESSEL STEELS
    STEELE, LE
    ATOMIC ENERGY REVIEW, 1969, 7 (02) : 3 - &
  • [40] Recent progress in understanding reactor pressure vessel steel embrittlement
    Odette, GR
    Lucas, GE
    RADIATION EFFECTS AND DEFECTS IN SOLIDS, 1998, 144 (1-4): : 189 - 231