SUMMARY OF GAS-COOLED REACTOR PROGRAMS

被引:18
|
作者
GOODJOHN, AJ
机构
[1] Gas-Cooled Reactor Associates, San Diego, CA 92121
关键词
D O I
10.1016/0360-5442(91)90089-5
中图分类号
O414.1 [热力学];
学科分类号
摘要
This report has been compiled by Gas-Cooled Reactor Associates (GCRA) as a central source of summary-level information on the present status of High-Temperature Gas-Cooled Reactor (HTGR) programs in the world and on future plans for the continued development and deployment of HTGRs. Most of the information concerns the programs in the United States, the Federal Republic of Germany, Japan, and the Soviet Union; countries that have had large programs related to HTGR technology for several years. Summary-level information is also provided in the report on the nature of the HTGR-related efforts in several other countries who either have an increasing interest in the technology and/or who are performing some development effort related to HTGR technology. Similarly, the report contains an summary-level update on the MAGNOX and AGR reactor programs, in recognition that these gas-cooled reactors were predecessors of the HTGR and have provided some of the bases from which the HTGR has evolved. Most of the new information for this report was gathered from material presented at the Eleventh International Conference on the HTGR held in Dimitrovgrad, USSR on June 19-20, 1989, the subsequent International Atomic Energy Agency Technical Committee Meeting on Gas-Cooled Reactor Technology, Safety and Siting held at the same site on June 21-23, 1989, and from several correspondents closely connected on a regular basis with the activities discussed.
引用
收藏
页码:79 / 106
页数:28
相关论文
共 50 条
  • [21] DISCUSSION OF FUTURE TECHNOLOGY OF GAS-COOLED REACTOR
    CARRUTHE.
    VAUGHAN, RD
    BANGASH
    WEBB
    GRIFFITHS
    VAUGHAN
    CAVE
    WHITEHOU.
    HAFTKE
    FAIR
    JOURNAL OF THE BRITISH NUCLEAR ENERGY SOCIETY, 1969, 8 (02): : 145 - &
  • [22] The gas-cooled reactor, current development status
    Kraemer, H.
    Kerntechnik und Atompraxis, 1978, 20 (8-9): : 357 - 361
  • [23] THE GAS-COOLED FAST-REACTOR IN 1981
    GRATTON, CP
    NUCLEAR ENERGY-JOURNAL OF THE BRITISH NUCLEAR ENERGY SOCIETY, 1981, 20 (04): : 287 - 295
  • [24] CONCEPTUAL DESIGN OF A GAS-COOLED TOKAMAK REACTOR
    SAKO, K
    OHTA, M
    SEKI, Y
    YAMATO, H
    HIRAOKA, T
    TANAKA, K
    ASAMI, N
    MORI, S
    NUCLEAR FUSION, 1974, : 27 - 49
  • [25] APPLICATION OF ADVANCED GAS-COOLED REACTOR MATERIALS
    HENDERSON, L
    STEAD, R
    NUCLEAR TECHNOLOGY, 1976, 29 (02) : 174 - 190
  • [26] An ORNL code for gas-cooled reactor simulations
    Ball, SJ
    Nypaver, DJ
    Wichner, RP
    PROCEEDINGS OF THE INTERNATIONAL TOPICAL MEETING ON ADVANCED REACTORS SAFETY, VOLS 1 AND 2, 1997, : 961 - 964
  • [27] Gas-cooled fast reactor fuel fabrication
    Fielding, Randall
    Meyer, Mitch
    Jue, Jan-Fong
    Gan, Jian
    JOURNAL OF NUCLEAR MATERIALS, 2007, 371 (1-3) : 243 - 249
  • [28] Coupled simulations for prismatic gas-cooled reactor
    Podila, K.
    Chen, Q.
    Huang, X.
    Li, C.
    Rao, Y.
    Waddington, G.
    Jafri, T.
    NUCLEAR ENGINEERING AND DESIGN, 2022, 395
  • [29] Sensitivity Analysis of Gas-cooled Fast Reactor
    Lueley, Jakub
    Cerba, Stefan
    Vrban, Branislav
    Hascik, Jan
    24TH INTERNATIONAL CONFERENCE NUCLEAR ENERGY FOR NEW EUROPE, (NENE 2015), 2015,
  • [30] A gas-cooled reactor surface power system
    Lipinski, RJ
    Wright, SA
    Lenard, RX
    Harms, GA
    SPACE TECHNOLOGY AND APPLICATIONS INTERNATIONAL FORUM - 1999, PTS ONE AND TWO, 1999, 458 : 1470 - 1475