ANALOG SIMULATED EARTHQUAKE RESPONSE OF EXPERIMENTAL GAS-COOLED REACTOR

被引：0
|
作者：
IBANEZ, P
SMITH, CB
MATTHIES.RB
机构：
来源：
TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY | 1969年 / 12卷 / 02期
关键词：
D O I：
暂无
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：
引用
收藏
页码：782 / &
相关论文
共 50 条
  • [21] The design of the enhanced gas-cooled reactor (EGCR)
    Beaumont, HM
    Cheyne, A
    Gilroy, J
    Hulme, G
    Lennox, TA
    Sunderland, RE
    Every, DP
    ADVANCED REACTORS WITH INNOVATIVE FUELS, WORKSHOP PROCEEDINGS, 2002, : 313 - 323
  • [22] DECOMMISSIONING WINDSCALE ADVANCED GAS-COOLED REACTOR
    LAWTON, H
    PROCEEDINGS OF THE INSTITUTION OF MECHANICAL ENGINEERS PART A-JOURNAL OF POWER AND ENERGY, 1985, 199 (02) : 129 - 133
  • [23] REACTOR PHYSICS OF ADVANCES GAS-COOLED REACTORS
    TYROR, JG
    TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1964, 7 (01): : 162 - &
  • [24] GAS-COOLED BREEDER REACTOR PROGRAM IN THE USA
    SCOVILLE, JJ
    SIMON, RH
    TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1979, 31 (MAY): : 24 - 27
  • [25] 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 - &
  • [26] The gas-cooled reactor, current development status
    Kraemer, H.
    Kerntechnik und Atompraxis, 1978, 20 (8-9): : 357 - 361
  • [27] THE GAS-COOLED FAST-REACTOR IN 1981
    GRATTON, CP
    NUCLEAR ENERGY-JOURNAL OF THE BRITISH NUCLEAR ENERGY SOCIETY, 1981, 20 (04): : 287 - 295
  • [28] 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
  • [29] APPLICATION OF ADVANCED GAS-COOLED REACTOR MATERIALS
    HENDERSON, L
    STEAD, R
    NUCLEAR TECHNOLOGY, 1976, 29 (02) : 174 - 190
  • [30] 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
12345