NUCLEAR SAFETY OF SPENT FUEL POOL STORAGE AT NUCLEAR POWER PLANTS WITH VVER-1000: PHYSICAL PRINCIPLES AND STRUCTURAL SOLUTIONS

被引:0
|
作者
Osadchii, A. I. [1 ]
机构
[1] Kurchatov Inst, Natl Res Ctr, Inst Nucl Res, Moscow, Russia
关键词
Nuclear Power Plant; Fuel Element; Fuel Assembly; Water Density; Normal Operating Condition;
D O I
10.1007/s10512-011-9382-8
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
The physical principles and structural solutions concerning nuclear safety in handling nuclear fuel at nuclear power plants with VVER-1000 are examined. It is shown that a structure of storage racks in the holding pools based on the spacing of hexahedral boron steel pipes, the structure acting as a combined neutron trap, will increase the pool capacity as compared with the loosely packed pools and will make the handling of nuclear fuel nuclear safe under normal operating conditions and during accidents. In the future, this construction will make it possible to use fuel assemblies with high uranium content and fuel enrichment above 5%.
引用
收藏
页码:1 / 5
页数:5
相关论文
共 50 条
  • [31] DAMAGE TO THE OUTPUT MANIFOLDS OF STEAM-GENERATORS AT NUCLEAR-POWER-PLANTS WITH VVER-1000 REACTORS
    BARANENKO, VI
    KIROV, VS
    KRAVCHENKO, VP
    KOROVKIN, VA
    FRIDMAN, NA
    ATOMIC ENERGY, 1993, 75 (05) : 896 - 899
  • [32] SPENT FUEL STORAGE BASIS FOR NEW NUCLEAR-POWER PLANTS
    RUBINSTEIN, HJ
    CLARK, PM
    GILCREST, JD
    TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1977, 26 : 254 - 256
  • [33] ANALYSES OF SEVERE ACCIDENT SEQUENCES IN THE SPENT FUEL POOL OF THE VVER-1000 TYPE OF REACTOR WITH MELCOR 1.8.6
    Kotouc, Miroslav
    PROCEEDINGS OF THE 22ND INTERNATIONAL CONFERENCE ON NUCLEAR ENGINEERING - 2014, VOL 3, 2014,
  • [34] PROBABILISTIC SAFETY ASSESSMENT FOR CAP NUCLEAR POWER PLANT SPENT FUEL POOL
    Xu Yiquan
    Zhuo Yucheng
    Yang Yajun
    Fu Hao
    PROCEEDINGS OF THE 25TH INTERNATIONAL CONFERENCE ON NUCLEAR ENGINEERING, 2017, VOL 4, 2017,
  • [35] Investigation of Criticality and Relative Power Density Distribution in VVER-1000 Nuclear Power Reactor
    Genc, Yasin
    Uzun, Sinem
    Acir, Adem
    JOURNAL OF POLYTECHNIC-POLITEKNIK DERGISI, 2020, 23 (04): : 1379 - 1385
  • [36] Safety margin and fuel cycle period enhancements of VVER-1000 nuclear reactor using water/silver nanofluid
    Saadati, Hassan
    Hadad, Kamal
    Rabiee, Ataollah
    NUCLEAR ENGINEERING AND TECHNOLOGY, 2018, 50 (05) : 639 - 647
  • [37] The method of control of nuclear power plant with VVER-1000 reactor in maneuverable mode
    Maksimov, M.V.
    Tsiselskaya, T.A.
    Kokol, E.A.
    Journal of Automation and Information Sciences, 2015, 47 (06) : 17 - 32
  • [38] The reliability of high-pressure regeneration systems at power units of nuclear electric power plants with VVER-1000 and VVER-400 reactors
    Baranenko, V.I., 1600, Ministry of Atomic Energy and Industry, Moscow, Russian Federation (78):
  • [39] Sensitivity studies in spent fuel pool criticality safety analysis for APR-1400 nuclear power plants
    Al Awad, Abdulrahman S.
    Habashy, Abdalla
    Metwally, Walid A.
    NUCLEAR ENGINEERING AND TECHNOLOGY, 2018, 50 (05) : 709 - 716
  • [40] Investigation of the Dual-Cooled Annular Fuel Effect on the Thermal Power Uprate in a VVER-1000 Nuclear Reactor
    Ansarifar, G. R.
    Esteki, M. H.
    Zaidabadi, M.
    NUCLEAR TECHNOLOGY, 2016, 195 (01) : 105 - 109