Investigation of radiation creep of reactor graphite

被引：2
|
作者：
Subbotin, A. V. [1 ]
Pokrovskii, A. S. [2 ]
Khar'kov, D. V. [2 ]
机构：
[1] Dollezhal Res & Design Inst Elect Technol, Moscow, Russia
[2] Res Inst Nucl Reactors, State Sci Ctr Russian Federat, Dimitrovgrad, Russia
来源：
ATOMIC ENERGY | 2008年 / 105卷 / 02期
关键词：
Creep Deformation; Irradiation Temperature; Dimensional Change; Loaded Sample; Neutron Fluence;
D O I：
10.1007/s10512-008-9072-3
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：
The results of investigations of the radiation creep of GR-280 graphite under a high compression load (about 15 MPa) after irradiation in a BOR-60 reactor at 520A degrees C to fast-neutron fluence 1.2 center dot 10(22) cm(-2) are presented. It is shown that the fluence dependence of the creep deformation, calculated using the standard relation as the difference of the change in the dimensions of loaded and control samples, is anomalous. The linear thermal expansion coefficients of loaded and control samples are found as functions of the neutron fluence under the same conditions. It is noted that the linear thermal expansion coefficient of the samples irradiated under a load is much higher than that of the control samples. Simmons' theorem is used to take account of the effect of a load on the linear thermal expansion coefficient, and the dimensional changes of graphite exposed to radiation and the dependence of the true creep deformation on the neutron fluence are calculated. It is shown that these dependences are close to linear in the experimental fluence range (0.4-1.2)center dot 10(22) cm(-2).
引用
收藏
页码：104 / 109
页数：6
相关论文
共 50 条
  • [21] THEORY OF IRRADIATION CREEP IN REACTOR GRAPHITE - DISLOCATION PINNING-UNPINNING MODEL
    KELLY, BT
    FOREMAN, AJ
    CARBON, 1973, 11 (06) : 694 - 694
  • [22] THEORY OF IRRADIATION CREEP IN REACTOR GRAPHITE - DISLOCATION PINNING-UNPINNING MODEL
    KELLY, BT
    FOREMAN, AJE
    CARBON, 1974, 12 (02) : 151 - 158
  • [23] Radiation resistance of the reactor grade graphite with increased operational properties
    Lebedev, I.G.
    Kochkarev, O.G.
    Atomnaya Energiya, 2001, 91 (02): : 114 - 120
  • [24] RADIATION-DAMAGE IN GRAPHITE AND ITS RELEVANCE TO REACTOR DESIGN
    KELLY, BT
    PROGRESS IN NUCLEAR ENERGY, 1978, 2 (04) : 219 - 269
  • [25] DIMENSIONAL CHANGES AND RADIATION CREEP IN GRAPHITE AT VERY HIGH NEUTRON DOSES
    SIMMONS, JHW
    PERKS, AJ
    NATURE, 1965, 206 (4984) : 610 - &
  • [26] DIMENSIONAL CHANGES AND RADIATION CREEP OF GRAPHITE AT VERY HIGH NEUTRON DOSES
    PERKS, AJ
    SIMMONS, JHW
    CARBON, 1966, 4 (01) : 85 - &
  • [27] Investigation of radioactive contamination of graphite samples from the AM reactor
    Bushuev, A. V.
    Petrova, E. V.
    Kozhin, A. F.
    Shtyfurko, A. I.
    Masalov, D. P.
    ATOMIC ENERGY, 2006, 101 (05) : 816 - 821
  • [28] Investigation of radioactive contamination of graphite samples from the AM reactor
    A. V. Bushuev
    E. V. Petrova
    A. F. Kozhin
    A. I. Shtyfurko
    D. P. Masalov
    Atomic Energy, 2006, 101 : 816 - 821
  • [29] Investigation of reactor graphite processing with the carbon-14 retention
    Ojovan, MI
    Karlina, OK
    Klimov, VL
    Bergman, GA
    Pavlova, GY
    Yurchenko, AY
    Dmitriev, SA
    SCIENTIFIC BASIS FOR NUCLEAR WASTE MANAGEMENT XXVI, 2003, 757 : 615 - 620
  • [30] MEASUREMENT AND CONTROL OF RADIATION-INDUCED GROWTH OF BROOKHAVEN GRAPHITE REACTOR
    SINGER, RM
    THOMPSON, D
    TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1965, S 8 : 29 - &
12345