Analysis of embrittlement of WWER-1000 RPV materials

被引：31
|
作者：
Margolin, B. Z. [1 ]
Nikolayev, V. A. [1 ]
Yurchenko, E. V. [1 ]
Nikolayev, Yu A. [2 ]
Erak, D. Yu [2 ]
Nikolayeva, A. V. [2 ]
机构：
[1] CRISM Prometey, St Petersburg 191015, Russia
[2] NRC Kurchatov Inst, Moscow, Russia
来源：
INTERNATIONAL JOURNAL OF PRESSURE VESSELS AND PIPING | 2012年 / 89卷
关键词：
WWER-1000; reactor; Thermal aging; Neutron irradiation; Radiation embrittlement; Alloying elements; PROMETEY LOCAL APPROACH; BRITTLE-FRACTURE; RADIATION EMBRITTLEMENT;
D O I：
10.1016/j.ijpvp.2011.11.003
中图分类号：
T [工业技术];
学科分类号：
08 ;
摘要：
Analysis of embrittlement for WWER-1000 RPV materials is performed on the basis of available and original experimental data. Contributions of thermal aging and neutron irradiation to embrittlement are considered for base and weld metals. Equations have been obtained for the shift of the critical temperature of brittleness as a function of irradiation time and neutron fluence. For weld metal with high nickel content the dependence of the radiation embrittlement coefficient on the content of alloying elements affecting material embrittlement such as nickel, manganese and silicon has been obtained. (C) 2011 Elsevier Ltd. All rights reserved.
引用
收藏
页码：178 / 186
页数：9
相关论文
共 50 条
  • [21] Radiation Embrittlement of Cr-Ni-Mo and Cr-Mo RPV Steels
    Nikolaev, Yu. A.
    EFFECTS OF RADIATION ON MATERIALS: 23RD INTERNATIONAL SYMPOSIUM, 2008, 1492 : 56 - 72
  • [22] THE USE OF MASTER CURVE METHOD FOR STATISTICAL RE-EVALUATION OF SURVEILLANCE TEST DATA FOR WWER-1000 REACTOR PRESSURE VESSELS
    Revka, V. M.
    Grynik, E. U.
    Chyrko, L. I.
    STRENGTH OF MATERIALS, 2010, 42 (06) : 705 - 710
  • [23] Estimation of yield strength due to neutron irradiation in a pressure vessel of WWER-1000 reactor based on the correction of the secondary displacement model
    Moslemi-Mehni, Elaheh
    Khoshahval, Farrokh
    Pour-Imani, Reza
    Amirkhani-Dehkordi, M. A.
    NUCLEAR ENGINEERING AND TECHNOLOGY, 2023, 55 (09) : 3229 - 3240
  • [24] On the link of the embrittlement mechanisms and microcrack nucleation and propagation properties for RPV steels. Part II. Fracture properties and modelling
    Margolin, Boris
    Fomenko, Valentin
    Shvetsova, Victoria
    Yurchenko, Elena
    ENGINEERING FRACTURE MECHANICS, 2022, 270
  • [25] Evolution of the nanostructure of VVER-1000 RPV materials under neutron irradiation and post irradiation annealing
    Miller, M. K.
    Chernobaeva, A. A.
    Shtrombakh, Y. I.
    Russell, K. F.
    Nanstad, R. K.
    Erak, D. Y.
    Zabusov, O. O.
    JOURNAL OF NUCLEAR MATERIALS, 2009, 385 (03) : 615 - 622
  • [26] Numerical and experimental investigation of 3D coolant temperature distribution in the hot legs of primary circuit of reactor plant with WWER-1000
    Saunin, Yu.
    Dobrotvorski, A.
    Semenikhin, A.
    Ryasny, S.
    Kulish, G.
    Abdullaev, A.
    KERNTECHNIK, 2015, 80 (04) : 366 - 372
  • [27] THE DEVELOPMENT OF A THREE-DIMANSIONAL MODEL OF WWER-1000 CORE USING THE MONTE CARLO SERPENT CODE FOR NEUTRON-PHYSICAL MODELING
    Gulik, V., I
    Trofymenko, O. R.
    Galchenko, V. V.
    Budik, D., V
    PROBLEMS OF ATOMIC SCIENCE AND TECHNOLOGY, 2019, (05): : 58 - 61
  • [28] Neutron and Thermal Embrittlement of RPV Steels: An Overview
    Nanstad, Randy K.
    Sokolov, Mikhail A.
    Ortner, Susan R.
    Styman, Paul D.
    INTERNATIONAL REVIEW OF NUCLEAR REACTOR PRESSURE VESSEL SURVEILLANCE PROGRAMS, 2018, 1603 : 68 - 106
  • [29] Empirical correlation of observed three stages of fast neutron irradiation hardening and embrittlement in WWER-440 pressure vessel materials
    Levit, VI
    Korolev, YN
    Tipping, P
    Lessa, RNT
    EFFECTS OF RADIATION ON MATERIALS: 18TH INTERNATIONAL SYMPOSIUM, 1999, 1325 : 541 - 555
  • [30] Monitoring of Radiation Embrittlement of the First and Second Generation of VVER RPV Steels
    Shtrombakh, Ya. I.
    Nikolaev, Yu. A.
    EFFECTS OF RADIATION ON MATERIALS: 23RD INTERNATIONAL SYMPOSIUM, 2008, 1492 : 26 - 43
12345