LOCATION SYSTEMS-ANALYSIS OF AWAY-FROM-REACTOR SPENT FUEL-STORAGE FACILITIES

被引:0
|
作者
COHON, JL [1 ]
REVELLE, CS [1 ]
SHOBRYS, DE [1 ]
MARGULIES, TS [1 ]
HEREFORD, LG [1 ]
EAGLES, TW [1 ]
机构
[1] JOHNS HOPKINS UNIV, BALTIMORE, MD 21218 USA
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:152 / 154
页数:3
相关论文
共 38 条
  • [1] DESIGN COMPARISONS FOR AWAY-FROM-REACTOR SPENT-FUEL STORAGE BASINS
    KING, FD
    BLACK, JE
    [J]. TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1978, 28 (JUN): : 331 - 331
  • [2] TENNESSEE-VALLEY-AUTHORITY AWAY-FROM-REACTOR SPENT-FUEL STORAGE STUDIES
    DAVIDSON, RH
    [J]. TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1979, 32 (JUN): : 414 - 414
  • [3] AWAY-FROM-REACTOR FUEL-ELEMENT STORAGE AND TRANSPORTATION OF NUCLEAR WASTE
    LAWRENCE, MJ
    [J]. TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1979, 32 (JUN): : 100 - 101
  • [4] PROTOTYPE AWAY-FROM-REACTOR STORAGE FACILITY FOR WWER-TYPE SPENT FUEL - TECHNICAL FEATURES AND SAFEGUARD CONCEPT
    BURMESTER, M
    REHAK, W
    WILLUHN, K
    [J]. KERNENERGIE, 1989, 32 (02): : 57 - 62
  • [5] IAEA SAFEGUARDS ALTERNATIVE CONCEPTS FOR REACTOR SPENT FUEL-STORAGE AND DISPOSAL
    ERMAKOV, SV
    PUSHKAREV, VI
    [J]. KERNENERGIE, 1989, 32 (02): : 68 - 71
  • [6] FUEL-ROD CONSOLIDATION - A KEY PROCESS IN SPENT FUEL-STORAGE SYSTEMS
    HALEY, J
    FESLER, AA
    [J]. TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1982, 40 : 149 - 150
  • [7] POOL SYSTEMS FOR SPENT-FUEL INTERIM STORAGE FACILITIES
    HENNINGS, U
    HAURY, G
    REINEKE, HH
    [J]. TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1979, 31 (MAY): : 555 - 556
  • [8] METHODS OF CRITICALITY ANALYSIS FOR SPENT-FUEL STORAGE FACILITIES
    BROWN, CO
    HANSEN, LE
    [J]. TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1978, 28 (JUN): : 305 - 307
  • [9] EMPIRICAL DETERMINATION OF CESIUM RELEASE RATE COEFFICIENT FROM SEVERELY DEFECTED FUEL IN A SPENT FUEL-STORAGE POOL
    GILLESPIE, SG
    [J]. TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1984, 47 : 93 - 94
  • [10] An analysis of burnup reactivity credit for reactor RA spent fuel storage
    Milosevic, MJ
    Pesic, MP
    [J]. NUCLEAR ENGINEERING AND DESIGN, 1998, 180 (01) : 29 - 35