Advanced Search
Volume 34 Issue 3
Jul.  2017
Turn off MathJax
Article Contents

ZHU Shengyun, YUAN Daqing. Study of Radiation Properties of Structural Materials for Advanced Nuclear Energy Systems[J]. Nuclear Physics Review, 2017, 34(3): 302-309. doi: 10.11804/NuclPhysRev.34.03.302
Citation: ZHU Shengyun, YUAN Daqing. Study of Radiation Properties of Structural Materials for Advanced Nuclear Energy Systems[J]. Nuclear Physics Review, 2017, 34(3): 302-309. doi: 10.11804/NuclPhysRev.34.03.302

Study of Radiation Properties of Structural Materials for Advanced Nuclear Energy Systems

doi: 10.11804/NuclPhysRev.34.03.302
Funds:  Major Program of National Natural Science Foundation of China (91126002); Major Program of Pressurized Water Reactor(2012ZX06004-005); IAEA CRP(15165/R0); National Basic Research Program of China (973 Program)(G1999022600, 2007CB209900)
  • Received Date: 2016-12-25
  • Rev Recd Date: 2017-04-07
  • Publish Date: 2017-07-18
  • This paper introduces briefly the development of nuclear energy systems from the GEN I to the advanced GEN IV, the progress of manufacturing radiation resistant materials associated with the development of nuclear energy systems and the new methods of investigating radiation properties of the structural materials for the GEN IV nuclear energy systems at first. Irradiation induced deterioration of materials properties is a bottle neck problem, which must be investigated and solved for the development of the GEN IV nuclear energy systems. Unfortunately, all the currently available neutron sources cannot meet the requirements of investigating radiation properties of structural materials irradiated by high dose neutron irradiation in the GEN IV nuclear energy systems. Therefore, two new methods of the accelerator heavy ion irradiation that simulates the high-dose neutron irradiation and the triple beam irradiation that mimics the real neutron irradiation environment in the GEN IV nuclear energy systems have been developed. These two methods are introduced in this paper. The present status of the study on radiation properties of structural materials for nuclear energy systems of the new generation and the near future development plan at China Institute of Atomic Energy (CIAE) are described also. The accelerator heavy ion irradiation facilities for different applications and the simultaneous triple beam irradiation platform with three separate accelerators or implanters have been established at the HI-13 tandem accelerator of CIAE. A series of structural materials for nuclear energy systems, such as the home-made modified austenic steel, CLAM steel, 1515 steel, Tantalum, Tungsten, etc. have been tested and investigated systematically. A superconducting linear accelerator and a variable energy heavy ion cyclotron have been imported from abroad for a better performance of the study. Combined with the currently existing facilities of 2×13 MeV and 2×1.7 MV tandem accelerators, 30 and 100 MeV proton cyclotrons, China experimental fast reactor, China advance research reactor, Miniature neutron source reactor, etc. a comprehensive and advanced system of experimental irradiation platform for structural materials of nuclear energy systems will be established in the near future for both domestic and foreign users.
  • [1]

    百度百科,第四代核能系统[EB/OL]. [2016-11-10]https://baike.baidu.com/item/%E7%AC%AC%E5%9B%9B%E4%BB%A3%E6%A0%B8%E8%83%BD%E7%B3%BB%E7%BB%9F/355515?fr=aladdin

    百度百科,第四代核能系统[EB/OL]. https://baike.baidu.com/item/%E7%AC%AC%E5%9B%9B%E4%BB%A3%E6%A0%B8%E8%83%BD%E7%B3%BB%E7%BB%9F/355515?fr=aladdin

    [2] RACHKOV V I, KALYAKIN G, KUKHARCHUK O F, et al. Thermal Engineering, 2014, 61(5):327.
    [3] ZINKLE S J, BUSBY J T. Materials Today, 2009, 12:12.
    [4] YVON P, CARRE F. Journal of Nuclear Materials, 2008, 385:217.
    [5] ALLEN T, BUSBY J, MEYER M, et al. Materials Today, 2010, 13:14.
    [6] MURTY K L, CHARIT I. Journal of Nuclear Materials, 2008, 38:189.
    [7] KULCINSKJ G L, DORAN D G, ABDOU M A. ASTM Report 74-28, 1977:329.
    [8] PACKAN N H, FARRELL K, STIEGLER J O. Journal of Nuclear Materials 1978, 78:143.
    [9] KULCINSKI G L, LAIDLER J J, DORAN D G, et al. Radiation Effects, 1971, 7(3-4):195.
    [10] NELSON R S, MAZEY D J, HUDSON J A, et al. Journal of Nuclear Materials, 1970, 37(1):1.
    [11] ABROMEIT C. Journal of Nuclear Materials, 1994, 216:78.
    [12] LEWIS M B, PACKAN N H, WELLS G F, et al. Nucl Instr Meth, 1979, 167(2):233.
    [13] NEKLYUDOV V Z I, OZHIGOV L, VOYEVODIN V, et al. Proceedings of ACC Appl 2007:275.
    [14] ZELENSKIJ V F, NEKLYUDOV I M. Trans Tech Publications, 1992, 97:429.
    [15] ASTM E521, 2009, "Standard Practice for Neutron Radiation Damage Simulation by Charged-Particle Irradiation," ASTM International, West Conshohocken, PA, doi: 10.1520/E0521-96R09E01.
    [16]

    GARNER F A, SHAO L, OLOCZKO M B, et al. Use of Self-Ion Bombardment to Study Void Swelling in Advanced Radiation-Resistant Alloys[EB/OL].[2016-11-10]. https://www.researchgate.net/publication/281188208.

    GARNER F A, SHAO L, OLOCZKO M B, et al. Use of Self-Ion Bombardment to Study Void Swelling in Advanced Radiation-Resistant Alloys, https://www.researchgate.net/publication/281188208.

    [17]

    BRYK V, BORODIN O, KALCHENKO A, et al. Ion Issues on Irradiation Behavior of Structural Materials at High Doses and Gas Concentrations[EB/OL].[2016-11-10]. https://www.researchgate.net/publication/259294088.

    BRYK V, BORODIN O, KALCHENKO A, et al. Ion Issues on Irradiation Behavior of Structural Materials at High Doses and Gas Concentrations, https://www.researchgate.net/publication/259294088.

    [18] GETTO E, SUN K, MONTERROSA A M, et al. Journal of Nuclear Materials, 2016, 480:159.
    [19] CHEN TIANYI, AYDOGAN E, JONATHAN G, et al. Journal of Nuclear Materials, 2015, 467:42.
    [20] ZHU Shengyun, LUO Qi, FAN Zhiguo, et al. Phys Lett, 199714:535
    [21] ZHU Shengyun, IWATA T, XU Yongjun, et al. Modern Physics Letters B, 2004, 18:881
    [22] FARRELL K, LEWIS M B, PACKAN N H, et al. Scripta Metallurgica, 1978, 12(12):1121.
    [23] SERRUY S Y, RUAULT M O, TROCELLIER P, et al. Comptes Rendus Physique, 2008, 9(3-4):437.
    [24] TROCELLIE R P, SERRUYS Y, MIRO S, et al. Nucl Instr Meth B, 2008, 266(12):3178.
    [25] BECK L, SERRUYS Y, MIRO S, et al. Journal of Materials Research, 2015, 30(09):1183.
    [26] SERRUY S Y, TROCELLIER P, MIRO S, et al. Journal of Nuclear Materials, 2009, 386:967.
    [27] LEWIS M B, ALLEN W R, BUHL R A, et al. Nucl Instr Meth B, 1989, 43(2):243.
    [28] SERRUYS Y, RUAULT M, TROCELLIER P, et al. Nucl Instr Meth B, 2005, 240(1):124.
    [29] PELLEGRINO S, TROCELLIER P, MIRO S, et al. Nucl Instr Meth B, 2012, 273:213.
    [30] KOHYAMA A, KATOH Y, ANDO M, et al. Fusion Engineering and Design, 2000, 51:789.
    [31] HAMADA S, MIWA Y, YAMAKI D, et al. Journal of Nuclear Materials, 1998, 258:383.
    [32] VOYEVODIN V, KUPRⅡYANNOVA Y, BRYK V, et al. Proceedings of IWSMT-12, Bregenz, Austria, 19-23 October, 2014.
    [33] TANAKA T, OKA K, OHNUKI S, et al. Journal of Nuclear Materials, 2004, 329-333:294.
    [34] SEKIMURA N, IWAI T, ARAI Y, et al. Journal of nuclear materials, 2000, 283:224.
    [35] Final Report on IAEA CRPSMoRE:"Accelerator Simula-tion and Theoretical Modelling of Radiation Effects", 2012.
    [36] ZHENG Yongnan, YI Zuo, XU Yongjun, et al. Problems of Atomic Science and Technology, 2009, 4:89.
    [37] ZHENG Yongnan, HUANG Junying, PENG Lei, et al. Plasma Science and Technology, 2012, 14:629.
    [38] HUANG Junying, LI Chunjing, LI Yanfen, et al. Journal of Nuclear Science and Engineering, 2007, 27:41. (in Chinese) (黄郡英,李春京,李艳芬, 等,核科学与工程, 2007, 27:41.)
    [39] YUAN Daqing, ZHENG Yongnan ZUO Yi, et al, Chin Phys Lett, 2014, 31:046101.
  • 加载中
通讯作者: 陈斌, bchen63@163.com
  • 1. 

    沈阳化工大学材料科学与工程学院 沈阳 110142

  1. 本站搜索
  2. 百度学术搜索
  3. 万方数据库搜索
  4. CNKI搜索

Article Metrics

Article views(1157) PDF downloads(259) Cited by()

Related
Proportional views

Study of Radiation Properties of Structural Materials for Advanced Nuclear Energy Systems

doi: 10.11804/NuclPhysRev.34.03.302
Funds:  Major Program of National Natural Science Foundation of China (91126002); Major Program of Pressurized Water Reactor(2012ZX06004-005); IAEA CRP(15165/R0); National Basic Research Program of China (973 Program)(G1999022600, 2007CB209900)

Abstract: This paper introduces briefly the development of nuclear energy systems from the GEN I to the advanced GEN IV, the progress of manufacturing radiation resistant materials associated with the development of nuclear energy systems and the new methods of investigating radiation properties of the structural materials for the GEN IV nuclear energy systems at first. Irradiation induced deterioration of materials properties is a bottle neck problem, which must be investigated and solved for the development of the GEN IV nuclear energy systems. Unfortunately, all the currently available neutron sources cannot meet the requirements of investigating radiation properties of structural materials irradiated by high dose neutron irradiation in the GEN IV nuclear energy systems. Therefore, two new methods of the accelerator heavy ion irradiation that simulates the high-dose neutron irradiation and the triple beam irradiation that mimics the real neutron irradiation environment in the GEN IV nuclear energy systems have been developed. These two methods are introduced in this paper. The present status of the study on radiation properties of structural materials for nuclear energy systems of the new generation and the near future development plan at China Institute of Atomic Energy (CIAE) are described also. The accelerator heavy ion irradiation facilities for different applications and the simultaneous triple beam irradiation platform with three separate accelerators or implanters have been established at the HI-13 tandem accelerator of CIAE. A series of structural materials for nuclear energy systems, such as the home-made modified austenic steel, CLAM steel, 1515 steel, Tantalum, Tungsten, etc. have been tested and investigated systematically. A superconducting linear accelerator and a variable energy heavy ion cyclotron have been imported from abroad for a better performance of the study. Combined with the currently existing facilities of 2×13 MeV and 2×1.7 MV tandem accelerators, 30 and 100 MeV proton cyclotrons, China experimental fast reactor, China advance research reactor, Miniature neutron source reactor, etc. a comprehensive and advanced system of experimental irradiation platform for structural materials of nuclear energy systems will be established in the near future for both domestic and foreign users.

ZHU Shengyun, YUAN Daqing. Study of Radiation Properties of Structural Materials for Advanced Nuclear Energy Systems[J]. Nuclear Physics Review, 2017, 34(3): 302-309. doi: 10.11804/NuclPhysRev.34.03.302
Citation: ZHU Shengyun, YUAN Daqing. Study of Radiation Properties of Structural Materials for Advanced Nuclear Energy Systems[J]. Nuclear Physics Review, 2017, 34(3): 302-309. doi: 10.11804/NuclPhysRev.34.03.302
Reference (39)

Catalog

    /

    DownLoad:  Full-Size Img  PowerPoint
    Return
    Return