Application of engineering methods on reactor pressure vessel integrity assessment

被引：0
|
作者：
Talja, H
Keinanen, H
机构：
来源：
ECF 11 - MECHANISMS AND MECHANICS OF DAMAGE AND FAILURE, VOLS I-III | 1996年
关键词：
D O I：
暂无
中图分类号：
TH [机械、仪表工业];
学科分类号：
0802 ;
摘要：
An easy-to-use integrated program system for fast engineering integrity assessment is presented. It has been specially tailored for analyses of pressurised thermal shock loading of reactor pressure vessels. The applicability of the program system is demonstrated with an integrity evaluation of a cladded VVER-440 type reactor pressure vessel under strip-like cooling. The results agree well with those of detailed finite element analyses at the deepest point of the crack.
引用
收藏
页码：2133 / 2138
页数：6
相关论文
共 50 条
  • [31] USING A PROBABILISTIC APPROACH IN THE BRITTLE FRACTURE DETERMINISTIC INTEGRITY ASSESSMENT OF A NUCLEAR REACTOR PRESSURE VESSEL
    Beaufils, Romain
    Meister, Eric
    Ardillon, Emmanuel
    PROCEEDINGS OF THE ASME PRESSURE VESSELS AND PIPING CONFERENCE, VOL 3: DESIGN AND ANALYSIS, 2012, : 967 - +
  • [32] EPRI activities to address reactor pressure vessel integrity issues
    Rosinski, ST
    Carter, RG
    NUCLEAR ENGINEERING AND DESIGN, 1999, 194 (2-3) : 199 - 204
  • [33] Application of reactor pressure vessel water lever during core damage assessment
    Wei, Yan-Song
    Li, Wen-Shuang
    Shi, Xiao-Lei
    Li, Zai-Peng
    Ji, Song-Tao
    Yuanzineng Kexue Jishu/Atomic Energy Science and Technology, 2014, 48 : 385 - 388
  • [34] Application of advanced NDT methods to assess structural integrity of pressure vessel welded joints
    Opacic, Mirjana
    Sedmak, Aleksandar
    Bakic, Gordana
    Milosevic, Nenad
    Milovanovic, Nikola
    23 EUROPEAN CONFERENCE ON FRACTURE, ECF23, 2022, 42 : 1185 - 1189
  • [35] Reactor pressure vessel design of the high temperature engineering test reactor
    Tachibana, Y
    Nakagawa, S
    Iyoku, T
    NUCLEAR ENGINEERING AND DESIGN, 2004, 233 (1-3) : 103 - 112
  • [36] Assessment of Residual Stress Due to Overlay-Welded Cladding and Structural Integrity of a Reactor Pressure Vessel
    Katsuyama, Jinya
    Nishikawa, Hiroyuki
    Udagawa, Makoto
    Nakamura, Mitsuyuki
    Onizawa, Kunio
    JOURNAL OF PRESSURE VESSEL TECHNOLOGY-TRANSACTIONS OF THE ASME, 2013, 135 (05):
  • [37] Deterministic and Probabilistic Fracture Mechanics Analysis for Structural Integrity Assessment of Pressurized Water Reactor Pressure Vessel
    Huang, Kuan-Rong
    Huang, Chin-Cheng
    Chou, Hsiung-Wei
    JOURNAL OF PRESSURE VESSEL TECHNOLOGY-TRANSACTIONS OF THE ASME, 2016, 138 (03):
  • [38] Structural integrity assessment of a closure head of a PWR reactor pressure vessel under pressurized thermal shock
    Naweed, Muhammad
    Murtaza, Usman Tariq
    Siddique, Waseem
    NUCLEAR ENGINEERING AND DESIGN, 2023, 409
  • [39] FRENCH REACTOR VESSEL INTEGRITY
    Churier, H.
    PROCEEDINGS OF THE ASME PRESSURE VESSELS AND PIPING CONFERENCE, PVP 2012, VOL 7: OPERATIONS, APPLICATIONS AND COMPONENTS, 2012, : 3 - 11
  • [40] U.S. and French approaches to reactor pressure vessel integrity
    Griesbach. T.
    Buchalet, C.
    Server, W.L.
    Welding Research Council Bulletin, 1993, (386): : 21 - 27
12345