FUEL-CYCLE ANALYSIS OF MOLTEN-SALT BREEDER REACTORS

被引:1
作者
BAUMAN, HF
KASTEN, PR
机构
来源
NUCLEAR APPLICATIONS | 1966年 / 2卷 / 04期
关键词
D O I
10.13182/NT66-A27518
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:287 / &
相关论文
共 12 条
  • [1] ALEXANDER LG, 1963, ANL6792, P553
  • [2] MOLTEN FLUORIDES AS POWER REACTOR FUELS
    BRIANT, RC
    WEINBERG, AM
    [J]. NUCLEAR SCIENCE AND ENGINEERING, 1957, 2 (06) : 797 - 803
  • [3] BRIGGS RB, ORNL3708
  • [4] CARR WH, 1964, J TENN ACAD SCI, V39, P44
  • [5] Cathers G.I., 1959, ORNL2661
  • [6] Grimes W.R., 1964, ORNL3708
  • [7] KASTEN PR, 1964, P INT C PEACEFUL USE
  • [8] KERLIN TW, 1964, ORNLTM847
  • [9] RECOVERING URANIUM SUBMARINE REACTOR FUELS
    MILFORD, RP
    MANN, S
    RUCH, JB
    CARR, WH
    [J]. INDUSTRIAL AND ENGINEERING CHEMISTRY, 1961, 53 (05): : 357 - 362
  • [10] Scott CD, 1966, ORNL3791