Materials science research for sodium cooled fast reactors

被引：14
|
作者：
Raj, Baldev [1 ]
机构：
[1] Indira Gandhi Ctr Atom Res, Kalpakkam 603102, Tamil Nadu, India
来源：
BULLETIN OF MATERIALS SCIENCE | 2009年 / 32卷 / 03期
关键词：
Nuclear energy; fast breeder reactors; materials science; stainless steels; sodium; THRESHOLD OXYGEN LEVELS; BREEDER TEST REACTOR; O SYSTEM; BEHAVIOR; STEEL; ELECTROLYTE; SIMULATION; COOLANT; FUEL;
D O I：
10.1007/s12034-009-0041-9
中图分类号：
T [工业技术];
学科分类号：
08 ;
摘要：
The paper gives an insight into basic as well as applied research being carried out at the Indira Gandhi Centre for Atomic Research for the development of advanced materials for sodium cooled fast reactors towards extending the life of reactors to nearly 100 years and the burnup of fuel to 2,00,000 MWd/t with an objective of providing fast reactor electricity at an affordable and competitive price.
引用
收藏
页码：271 / 283
页数：13
相关论文
共 50 条
  • [41] Gas detection in sodium cooled fast reactors: determination of a transfer function
    Ding, C.
    Filliatre, P.
    Desgranges, L.
    ANIMMA 2021 - ADVANCEMENTS IN NUCLEAR INSTRUMENTATION MEASUREMENT METHODS AND THEIR APPLICATIONS, 2021, 253
  • [42] Russian Codes for Safety Analysis of Sodium-Cooled Fast Reactors
    Rachkov, V. I.
    Khomyakov, Yu. S.
    Shvetsov, Yu. E.
    ATOMIC ENERGY, 2014, 116 (04) : 265 - 270
  • [43] Design of Neutron Flux Monitoring System for Sodium Cooled Fast Reactors
    Nagaraj, C. P.
    Sivaramakrishna, M.
    Madhusoodanan, K.
    Chellapandi, P.
    2013 3RD INTERNATIONAL CONFERENCE ON ADVANCEMENTS IN NUCLEAR INSTRUMENTATION, MEASUREMENT METHODS AND THEIR APPLICATIONS (ANIMMA), 2013,
  • [44] Russian Codes for Safety Analysis of Sodium-Cooled Fast Reactors
    V. I. Rachkov
    Yu. S. Khomyakov
    Yu. E. Shvetsov
    Atomic Energy, 2014, 116 : 265 - 270
  • [45] Numerical simulation of operational transients in sodium-cooled fast reactors
    Vikram, G.
    Rajendrakumar, M.
    Natesan, K.
    NUCLEAR ENGINEERING AND DESIGN, 2023, 402
  • [46] Safety Method for the Preconceptual Phase of Sodium-Cooled Fast Reactors
    Ehster, S.
    Ammirabile, L.
    Bubelis, E.
    Carluec, B.
    Droin, J. B.
    Girardi, E.
    JOURNAL OF NUCLEAR ENGINEERING AND RADIATION SCIENCE, 2022, 8 (01):
  • [47] STUDY AND TESTING OF COMPONENTS OF SECONDARY CIRCUITS OF FAST SODIUM COOLED REACTORS
    BEAUFRERE, J
    NEDELEC, J
    DEMONTAR.A
    ENERGIE NUCLEAIRE PARIS, 1972, 14 (01): : 17 - +
  • [48] Status of TRIO_U code for sodium cooled fast reactors
    Tenchine, D.
    Barthel, V.
    Bieder, U.
    Ducros, F.
    Fauchet, G.
    Fournier, C.
    Mathieu, B.
    Perdu, F.
    Quemere, P.
    Vandroux, S.
    NUCLEAR ENGINEERING AND DESIGN, 2012, 242 : 307 - 315
  • [49] Thermal striping limits for components of sodium cooled fast spectrum reactors
    Chellapandi, P.
    Chetal, S. C.
    Raj, Baldev
    NUCLEAR ENGINEERING AND DESIGN, 2009, 239 (12) : 2754 - 2765
  • [50] Development on fatigue testing of hardfaced components in sodium cooled fast reactors
    Pasarkar, Amruta
    Balaguru, S.
    ENGINEERING FAILURE ANALYSIS, 2022, 137
12345