Materials Creep Qualification Testing for Next Generation Nuclear Reactors

被引:0
|
作者
Hahner, Peter [1 ]
Hurst, Roger [1 ]
机构
[1] JRC Inst Energy, European Commiss, NL-1755 ZG Petten, Netherlands
关键词
nuclear reactors; Generation IV; high temperature creep; P91; ODS steels; nickel-base alloys; HIGH-TEMPERATURE; HELIUM; CHALLENGES; CORROSION;
D O I
暂无
中图分类号
TH [机械、仪表工业];
学科分类号
0802 ;
摘要
The development of next generation nuclear fission reactors, needed to replace or supplement the current designs of nuclear reactors within the next say 30 years., critically depends on the availability of advanced structural and functional materials systems which have to withstand extreme conditions: high temperatures, intense neutron irradiation, and strongly corrosive coolant environments, in combination with complex loading states and cyclic loading histories. The mechanical performance and reliability of those materials depend in which of the six candidate systems for Generation IV reactors they will be applied. This paper gives an overview of the six selected systems indicating where research on materials integrity, in particular under high temperature creep conditions, is still needed. Using examples taken from research projects in which the authors' laboratory has participated, the materials qualification high temperature testing for three crucial components, reactor pressure vessel and piping, gas turbines and heat exchangers is described in some detail. Finally pointers are derived as to not only the scale of the remaining research needs but also the mechanisms which are planned to be followed in Europe, not to mention globally, to obtain the required data and understanding.
引用
收藏
页码:112 / 124
页数:13
相关论文
共 50 条
  • [1] Materials qualification testing for next generation nuclear reactors
    Hurst, Roger
    Hahner, Peter
    [J]. BALTICA VIII: LIFE MANAGEMENT AND MAINTENANCE FOR POWER PLANTS, VOL 1, 2010, 264 : 324 - 350
  • [2] Research on the Thermophysics of Next-Generation Nuclear Reactors
    Sorokin, A. P.
    Poplavskii, V. M.
    Kozlov, F. A.
    Kuzina, Yu. A.
    Kamaev, A. A.
    Orlov, Yu. I.
    Trufanov, A. A.
    Chernonog, V. L.
    [J]. ATOMIC ENERGY, 2017, 123 (01) : 34 - 42
  • [3] Research on the Thermophysics of Next-Generation Nuclear Reactors
    A. P. Sorokin
    V. M. Poplavskii
    F. A. Kozlov
    Yu. A. Kuzina
    A. A. Kamaev
    Yu. I. Orlov
    A. A. Trufanov
    V. L. Chernonog
    [J]. Atomic Energy, 2017, 123 : 34 - 42
  • [4] Materials for generation-IV nuclear reactors
    Rodier, Aurore
    [J]. ADVANCED ENGINEERING MATERIALS, 2007, 9 (07) : 525 - 525
  • [5] Structural materials issues for the next generation fission reactors
    Chant I.
    Murty K.L.
    [J]. JOM, 2010, 62 (09) : 67 - 74
  • [6] Proceedings of the first symposium on nuclear fuels and structural materials for next generation nuclear reactors (NFSM-1) - Foreword
    Snead, Lance L.
    [J]. JOURNAL OF NUCLEAR MATERIALS, 2007, 371 (1-3) : IX - IX
  • [7] Proceedings of the Second Symposium on Nuclear Fuels and Structural Materials for Next Generation Nuclear Reactors (NFSM-2) Preface
    Snead, Lance
    Wiffen, Bill
    Allen, Todd
    [J]. JOURNAL OF NUCLEAR MATERIALS, 2009, 392 (02) : VII - VII
  • [8] PLACE OF MATERIALS TESTING REACTORS IN NUCLEAR POWER PROGRAMME
    JACKSON, RF
    HARRIES, DR
    WALTON, GN
    [J]. JOURNAL OF THE BRITISH NUCLEAR ENERGY SOCIETY, 1964, 3 (04): : 334 - &
  • [9] PLACE OF MATERIALS TESTING REACTORS IN NUCLEAR POWER PROGRAMME
    JACKSON, RF
    WALTON, GN
    HARRIES, DR
    [J]. JOURNAL OF THE BRITISH NUCLEAR ENERGY SOCIETY, 1964, 3 (02): : 149 - &
  • [10] Testing challenges for next generation radiological/nuclear detection
    Blumenthal, Daniel J.
    [J]. 2007 IEEE NUCLEAR SCIENCE SYMPOSIUM CONFERENCE RECORD, VOLS 1-11, 2007, : 166 - 169