RPV-1: A Virtual Test Reactor to simulate irradiation effects in light water reactor pressure vessel steels

被引:12
|
作者
Jumel, S [1 ]
Van-Duysen, JC [1 ]
机构
[1] Univ Sci & Technol Lille 1, LMPGM, F-56655 Villeneuve Dascq, France
关键词
D O I
10.1016/j.jnucmat.2004.10.131
中图分类号
T [工业技术];
学科分类号
08 ;
摘要
Many key components in commercial nuclear reactors are subject to neutron irradiation which modifies their mechanical properties. So far, the prediction of the in-service behavior and the lifetime of these components has required irradiations in so-called 'Experimental Test Reactors'. This predominantly empirical approach can now be supplemented by the development of physically based computer tools to simulate irradiation effects numerically. The devising of such tools, also called Virtual Test Reactors (VTRs), started in the framework of the REVE Project (REactor for Virtual Experiments). This project is a joint effort among Europe, the United States and Japan aimed at building VTRs able to simulate irradiation effects in pressure vessel steels and internal structures of LWRs. The European team has already built a first VTR, called RPV-1, devised for pressure vessel steels. Its inputs and outputs are similar to those of experimental irradiation programs carried out to assess the in-service behavior of reactor pressure vessels. RPV-1 is made of five codes and two databases which are linked up so as to receive, treat and/or convey data. A user friendly Python interface eases the running of the simulations and the visualization of the results. RPV-1 is sensitive to its inputs (neutron spectrum, temperature....) and provides results in conformity with experimental ones. The iterative improvement of RPV-1 has been started by the comparison of simulation results with the database of the WAR experimental program led by the University of California Santa Barbara. These first successes led 40 European organizations to start developing RPV-2, an advanced version of RPV-1, as well as INTERN-1, a VTR devised to simulate irradiation effects in stainless steels, in a large effort (the PERFECT project) supported by the European Commission in the framework of the 6th Framework Program. (c) 2004 Elsevier B.V. All rights reserved.
引用
收藏
页码:125 / 148
页数:24
相关论文
共 50 条
  • [1] Simulation of irradiation effects in light water reactor vessel steels - experimental validation of RPV-1
    Jumel, Stephanie
    Van Duysen, Jean-Claude
    JOURNAL OF NUCLEAR MATERIALS, 2007, 366 (1-2) : 256 - 265
  • [2] Irradiation effects in reactor pressure vessel steels
    Davies, M
    Bolton, C
    English, C
    Nicholson, R
    Priest, B
    Williams, T
    INTERNATIONAL JOURNAL OF PRESSURE VESSELS AND PIPING, 2002, 79 (8-10) : 619 - 620
  • [3] Simulation of irradiation effects in reactor pressure vessel steels: the Reactor for Virtual Experiments (REVE) project
    Jumel, S
    Domain, C
    Ruste, J
    Van Duysen, JC
    Becquart, C
    Legris, A
    Pareige, P
    Barbu, A
    Van Walle, E
    Chaouadi, R
    Hou, M
    Odette, GR
    Stoller, RE
    Wirth, BD
    JOURNAL OF TESTING AND EVALUATION, 2002, 30 (01) : 37 - 46
  • [4] Irradiation Damage Effects on Microstructure of Reactor Pressure Vessel Steels
    Li C.
    Li Y.
    Mo H.
    Liu F.
    Chen J.
    Shu G.
    1600, Atomic Energy Press (38): : 54 - 57
  • [5] Effects of neutron irradiation on precipitation in reactor pressure vessel steels
    Faulkner, R. G.
    Lu, Z.
    Ellis, D.
    Williams, T. J.
    EFFECTS OF RADIATION ON MATERIALS: 22ND SYMPOSIUM, 2006, 1475 : 165 - +
  • [6] Thermographic detection of fatigue damage of reactor pressure vessel (RPV) steels
    Yang, B
    Liaw, PK
    Wang, H
    Huang, JY
    Kuo, RC
    Huang, JG
    ELECTRON MICROSCOPY: ITS ROLE IN MATERIALS SCIENCE: THE MIKE MESHII SYMPOSIUM, 2003, : 191 - 200
  • [7] The effect of phosphorus on precipitation in irradiated reactor pressure vessel (RPV) steels
    Kamboj, Anshul
    Bachhav, Mukesh N.
    Dubey, Megha
    Almirall, Nathan
    Yamamoto, Takuya
    Marquis, Emmanuelle A.
    Odette, Robert
    JOURNAL OF NUCLEAR MATERIALS, 2023, 585
  • [8] Thermographic detection of fatigue damage of reactor pressure vessel (RPV) steels
    Yang, B
    JOURNAL OF MATERIALS ENGINEERING AND PERFORMANCE, 2003, 12 (03) : 345 - 353
  • [9] Thermographic detection of fatigue damage of reactor pressure vessel (RPV) steels
    Bing Yang
    Journal of Materials Engineering and Performance, 2003, 12 : 345 - 353
  • [10] PROGRESS IN LIGHT WATER-REACTOR PRESSURE-VESSEL STEELS
    KODAIRA, T
    TETSU TO HAGANE-JOURNAL OF THE IRON AND STEEL INSTITUTE OF JAPAN, 1987, 73 (14): : 1656 - 1667