Comparison of lead-and sodium-cooled fast-neutron reactors

被引:0
|
作者
V. A. Sidorenko
机构
来源
Atomic Energy | 1999年 / 86卷
关键词
Nuclear Power Plant; Reactor Technology; Safety Indicator; Inherent Safety; Successful Advancement;
D O I
暂无
中图分类号
学科分类号
摘要
The author expounds his point of view concerning the comparative advantages and drawbacks of two types of technology for liquid-metal fast-neutron reators: lead and sodium. It is concluded that there are no substantiation and no significant factors justifying forced implementation of a lead-cooled reactor, especially in the existing economic climate in Russia. Successful advancement of a new reactor technoloy is possible at present only if the technology is accepted internationally and the principal nuclear countires participate.
引用
收藏
页码:170 / 172
页数:2
相关论文
共 50 条
  • [1] Comparison of lead- and sodium-cooled fast-neutron reactors
    Sidorenko, VA
    ATOMIC ENERGY, 1999, 86 (03) : 170 - 172
  • [2] Instrumentation for Sodium-Cooled Fast Breeder Reactors
    Mishra, Govind Kumar
    Sakthivel, M.
    Swamy, S. L. N.
    Madhusoodanan, K.
    NUCLEAR SCIENCE AND ENGINEERING, 2013, 174 (01) : 96 - 102
  • [3] PUMPS FOR SODIUM-COOLED FAST BREEDER REACTORS
    ALLEN, RC
    REACTOR AND FUEL-PROCESSING TECHNOLOGY, 1969, 12 (03): : 264 - &
  • [4] Unanticipated accidents in sodium-cooled fast reactors
    Yu. E. Bagdasarov
    Atomic Energy, 2010, 108 : 165 - 169
  • [5] SAFETY OF SODIUM-COOLED FAST-REACTORS
    BAGDASAROV, YE
    KOCHETKOV, LA
    MATVEEV, VI
    KULAKOVSKII, MY
    KUZNETSOV, IA
    POMERANTSEV, GB
    KRASNOYAROV, NV
    SOVIET ATOMIC ENERGY, 1977, 43 (06): : 1114 - 1122
  • [6] UNANTICIPATED ACCIDENTS IN SODIUM-COOLED FAST REACTORS
    Bagdasarov, Yu. E.
    ATOMIC ENERGY, 2010, 108 (03) : 165 - 169
  • [7] Thermal-hydraulics, physical chemistry, and technology at nuclear power stations equipped with fast-neutron sodium-cooled reactors
    Alekseev V.V.
    Efanov A.D.
    Kozlov F.A.
    Sorokin A.P.
    Therm Eng, 2007, 12 (933-941): : 933 - 941
  • [8] In vessel neutron instrumentation for sodium-cooled fast reactors: Type, lifetime and location
    Filliatre, P.
    Jammes, C.
    Geslot, B.
    Buiron, L.
    ANNALS OF NUCLEAR ENERGY, 2010, 37 (11) : 1435 - 1442
  • [9] SODIUM-COOLED REACTORS
    DIETRICH, JR
    POWER REACTOR TECHNOLOGY, 1965, 8 (01): : 75 - &
  • [10] Decontamination of Sodium in the Primary Circuit of Fast Sodium-Cooled Reactors
    Rovneiko, A. V.
    Tashlykov, O. L.
    Filin, I. A.
    Khomyakov, A. P.
    Shcheklein, S. E.
    Sesekin, A. N.
    RADIOCHEMISTRY, 2024, 66 (05) : 656 - 662