Experimental and statistical analysis of radiation embrittlement (RE) of the WWER-440 vessel materials

被引：0
|
作者：
Nikolaeva, A.V. [1 ]
Nikolaev, Yu.A. [1 ]
Kevorkyan, Yu.P. [1 ]
机构：
[1] RNTs 'Kurchatovskij Inst', Moscow, Russia
来源：
Atomnaya Energiya | 2001年 / 90卷 / 04期
关键词：
Composition effects - Correlation methods - Data processing - Embrittlement - Neutron irradiation - Pressure vessels - Radiation effects - Welds;
D O I：
暂无
中图分类号：
学科分类号：
摘要：
The aim of the paper is statistical processing of the experimental data on the RE of materials, irradiated in the WWER-440 reactor. Results of the processing are expressed in obtaining the correlation dependences between the RE of the welded joint metal and the base metal (steel) of the reactor vessel on the neutron fluence and chemical composition of materials. These more reliable correlation dependences are developed and recommended for application.
引用
收藏
页码：260 / 268
相关论文
共 50 条
  • [21] Fracture mechanics characterisation of the WWER-440 reactor pressure vessel beltline welding seam
    Viehrig, Hans-Werner
    Schuhknecht, Jan
    INTERNATIONAL JOURNAL OF PRESSURE VESSELS AND PIPING, 2009, 86 (04) : 239 - 245
  • [22] Application of advanced master curve approaches on WWER-440 reactor pressure vessel steels
    Viehrig, Hans-Werner
    Scibetta, Marc
    Wallin, Kim
    INTERNATIONAL JOURNAL OF PRESSURE VESSELS AND PIPING, 2006, 83 (08) : 584 - 592
  • [23] THERMAL ANNEALING OF WWER-440 NUCLEAR REACTOR PRESSURE VESSEL INTERNALS: PRESENT STATUS
    Bursik, Ondrej
    Maresova, Barbora
    Petelova, Petra
    Kopriva, Radim
    Pesek, Pavel
    27TH INTERNATIONAL CONFERENCE ON METALLURGY AND MATERIALS (METAL 2018), 2018, : 658 - 662
  • [24] SCK•CEN contribution to the IAEA Round Robin exercise on WWER-440 RPV weld material:: irradiation, annealing and re-embrittlement
    Lucon, E
    van Walle, E
    Scibetta, M
    Chaouadi, R
    Willekens, M
    Wéber, M
    INTERNATIONAL JOURNAL OF PRESSURE VESSELS AND PIPING, 2002, 79 (8-10) : 667 - 686
  • [25] Neuronet analysis of the effect of alloying elements on the radiation embrittlement of VVER-440 vessel materials
    Obraztsov, S. M.
    Birzhevoi, G. A.
    Konobeev, Yu. V.
    Pechenkin, V. A.
    Rachkov, V. I.
    ATOMIC ENERGY, 2006, 101 (05) : 809 - 815
  • [26] Finite element-based vibration analysis of WWER-440 reactors
    Altstadt, E
    Weiss, FP
    NUCLEAR TECHNOLOGY, 1999, 128 (01) : 46 - 57
  • [27] Study of the beltline weld and base metal of WWER-440 first generation reactor pressure vessel
    J. Schuhknecht
    U. Rindelhardt
    H.-W. Viehrig
    Strength of Materials, 2010, 42 : 70 - 77
  • [28] STUDY OF THE BELTLINE WELD AND BASE METAL OF WWER-440 FIRST GENERATION REACTOR PRESSURE VESSEL
    Schuhknecht, J.
    Rindelhardt, U.
    Viehrig, H. -W.
    STRENGTH OF MATERIALS, 2010, 42 (01) : 70 - 77
  • [29] THEORETICAL AND EXPERIMENTAL-DETERMINATION OF THE TEMPERATURE DISTRIBUTION AT THE WWER-440 CORE INLET
    ACKERMANN, G
    DRAGER, P
    SIKLOSSY, P
    KERNENERGIE, 1985, 28 (07): : 293 - 297
  • [30] Application of Small Punch Testing Methods for Monitoring of WWER-440 Reactor Pressure Vessels Irradiation Embrittlement
    Petzova, Jana
    Kupca, Ludovit
    Brezina, Martin
    Bal'ak, Milos
    DETERMINATION OF MECHANICAL PROPERTIES OF MATERIALS BY SMALL PUNCH AND OTHER MINIATURE TESTING TECHNIQUES, 2ND INTERNATIONAL CONFERENCE SSTT, 2012, : 154 - 158
12345