A perspective on creep and fatigue issues in sodium cooled fast reactors

被引:0
|
作者
Baldev Raj
B. K. Choudhary
机构
[1] Indira Gandhi Centre for Atomic Research,
来源
Transactions of the Indian Institute of Metals | 2010年 / 63卷
关键词
Creep; fatigue; austenitic stainless steel; ferritic steel;
D O I
暂无
中图分类号
学科分类号
摘要
Development of advanced materials alongwith improved high temperature mechanical properties, particularly creep and fatigue are important and play a major role for the successful development of robust, safe and economical sodium cooled fast reactor (SFR) technology. The components of SFRs operate in demanding environments at high temperatures under complex creep, fatigue and creep-fatigue loading conditions. Based upon the service requirements in terms of different environments, temperature and loading conditions, different materials are chosen for different components. Ti modified 15Cr-15Ni austenitic stainless steel is chosen for clad and wrapper tubes in the reactor core, which experience high fast neutron flux of ∼ 1015 ncm−2s−1 along with high temperatures. Type 316L(N) SS is used for out-of-core structural components like main and inner vessels, and sodium pipelines. For steam generators, modified 9Cr-1Mo steel is chosen for all the components, where liquid sodium and steam/water coexist. Some of the important experiences and exciting achievements in the areas of in-house materials development and its characterization in terms of creep, low cycle fatigue and creep-fatigue properties important to design of reactor components for core, out-of-core and steam generator applications are described in the paper. Future directions for materials research and development activities involving critical issues like radiation damage resistance along with improved mechanical properties for advanced clad and wrapper materials necessary for achieving high fuel burnup and design life up to 60 years for out-of-core structural components leading to economical nuclear energy have been highlighted.
引用
收藏
页码:75 / 84
页数:9
相关论文
共 50 条
  • [1] A perspective on creep and fatigue issues in sodium cooled fast reactors
    Raj, Baldev
    Choudhary, B. K.
    TRANSACTIONS OF THE INDIAN INSTITUTE OF METALS, 2010, 63 (2-3) : 75 - 84
  • [2] Gas entrainment issues in sodium cooled fast reactors
    Tenchine, D.
    Fournier, C.
    Dolias, Y.
    NUCLEAR ENGINEERING AND DESIGN, 2014, 270 : 302 - 311
  • [3] An Overview of the Creep Research and Applications in Sodium Cooled Fast Spectrum Reactors
    Raj, Baldev
    Rao, K. Bhanu Sankara
    Mathew, M. D.
    Laha, K.
    Choudhary, B. K.
    CREEP & FRACTURE IN HIGH TEMPERATURE COMPONENTS: DESIGN & LIFE ASSESSMENT ISSUES, PROCEEDINGS, 2009, : 93 - 111
  • [4] Fuels for sodium-cooled fast reactors: US perspective
    Crawford, Douglas C.
    Porter, Douglas L.
    Hayes, Steven L.
    JOURNAL OF NUCLEAR MATERIALS, 2007, 371 (1-3) : 202 - 231
  • [5] Development on fatigue testing of hardfaced components in sodium cooled fast reactors
    Pasarkar, Amruta
    Balaguru, S.
    ENGINEERING FAILURE ANALYSIS, 2022, 137
  • [6] Creep-Fatigue Evaluation Methodologies and Related Issues for Japan Sodium Cooled Fast Reactor (JS']JSFR)
    Asayama, Tai
    Takaya, Shigeru
    Nagae, Yuji
    Ando, Masanori
    Tsukimori, Kazuyuki
    6TH INTERNATIONAL CONFERENCE ON CREEP, FATIGUE AND CREEP-FATIGUE INTERACTION, 2013, 55 : 309 - 313
  • [7] SODIUM-COOLED FAST-REACTORS - STRUCTURAL-MATERIALS ISSUES
    WOOD, DS
    METALS TECHNOLOGY, 1984, 11 (JUN): : 255 - 255
  • [8] Design challenges for sodium cooled fast reactors
    Konomura, Mamoru
    Ichimiya, Masakazu
    JOURNAL OF NUCLEAR MATERIALS, 2007, 371 (1-3) : 250 - 269
  • [9] Achieving the competitiveness of sodium cooled fast reactors
    Kochetkov, L.A.
    Malenkov, A.V.
    Poplavskij, V.N.
    Saraev, O.M.
    Suknev, K.L.
    Kiryushin, A.I.
    Atomnaya Energiya, 1997, 83 (06): : 401 - 405
  • [10] FAST BREEDER REACTORS COOLED BY SODIUM AND STEAM
    ENGELMANN, P
    KERNTECHNIK ISOTOPENTECHNIK UND CHEMIE, 1967, 9 (3-4): : 111 - +