期刊文献+

C276镍基合金中子辐照活化计算分析 被引量:1

Neutron irradiation activation calculation analysis of the C276 nickel alloy
在线阅读 下载PDF
导出
摘要 采用欧洲活化程序EASY-2007对C276的活化特性进行了活化计算与分析。计算所需中子能谱选取总中子通量约为2.47×1016n/cm2/s的瓦特裂变谱,辐照时间选取了0.5年、1年和1.5年三种情况。活化计算结果包括辐照停堆后不同冷却时间内C276活化产生的放射性活度、衰变余热及接触剂量率等。另外,本文将C276的活化特性与Zr-4及M5包壳材料作了初步的比较分析。结果表明,从中子活化角度看,C276与Zr-4相比并没有优势,但与M5相比还是有一定优势存在的。 C276 is one of the candidate cladding materials for the next-generation reactors and comprehensive resear- ches are under way to evaluate its characteristics. Activation inventory of C276 has been calculated and analyzed by u- sing the European Activation System EASY - 2007. Watt fission spectrum with the total neutron flux of 2.47×10^16 n/ cm2/s was employed, and the irradiation time of 0.5 year, lyear and 1.5years were chosen for the inventory calcula- tions. The concluded results include activity, afterheat and contact dose rate at shutdown. In addition, the preliminary comparison and analysis among the C276 and Zr-4, M5 on the activation characteristics were presented. The results indicate that C276 has no advantages comparing with Zr- 4, but has definite advantages comparing with M5 from the viewpoint of neutron activation.
出处 《华北电力大学学报(自然科学版)》 CAS 北大核心 2012年第6期105-108,共4页 Journal of North China Electric Power University:Natural Science Edition
基金 国家自然科学基金资助项目(10875042) 科技部"973"ITER国内配套重点项目(2009GB109003) 中央高校基本科研业务费专项基金资助(10ZG08)
关键词 C276 包壳 中子辐照 活化 C276 cladding neutron irradiation activation
  • 相关文献

参考文献7

  • 1赵文金,庞华.锆合金研究的国际动态[C].全国核材料学术交流会.成都,2006.
  • 2赵文金.核工业用高性能锆合金的研究[J].稀有金属快报,2004,23(5):15-20. 被引量:45
  • 3赵文金.法国压水堆燃料元件新一代包壳材料的发展[J].核动力工程,2000,21(3):278-284. 被引量:9
  • 4李德平,潘自强.辐射防护手册[M].北京:原子能出版社,1987.
  • 5Forrest R A. The European Activation System: EASY - 2007 Overview [ R]. UKAEA Report, UKAEA FUS 534, 2007.
  • 6Forrest R A. FISPACT - 2007: User Manual [ R ]. UKAEA Fusion, Report UKAEA FUS 534, 2007.
  • 7Forrest R A, Kopecky J, Sublet J Ch. The European Ac- tivation File: EAF - 2007 cross section library [ R ]. UKAEA Fusion, Report UKAEA FUS 535/537, 2007.

二级参考文献8

  • 16,Gilbon D,Soniak A,Doriot S,et al.Irradiation Creep and Growth Behavior and Microstructure Evolution of Advanced Zr-Base Alloys.ASTM STP 1354,Toronto,Ontario,Canada.1998.
  • 27,Forgeron T,Brachet JC,Barcelo F,et al.Experiment and Modelling of Advanced Fuel Rod Cladding Behavior under LOCA Conditions:α-β Phase Transformation Kinetics and EDGAR Methodology.ASTM STP 1354,Toronto,Ontario,Canada.1998.
  • 31,Mardon J P,Charquet D,Senevet J.Optimization of PWR Behavior of Stress Relieved Zircaloy-4 Cladding Tubes by Improving the Manufacturing and Inspection Process.Zirconium in the Nuclear Industr5y:Tenth International Symposium,ASTM STP 1245,American Society for Testing and Materials,Philadephia,1994,328~ 348.
  • 42,Mardon J P,Charquet D.Senevat J.Development of New Zirconium Alloys for PWR Fuel Rod Cladding,ANS West Palm Beach,1994,643~ 650.
  • 53,Mardon J P,Garner G,Beslu P,et al.Update on the Development of Advanced Zirconium Alloys for PWR Fuel Rod Cladding.ANS Fuel Performance Conference in Portland,1997,405~413.
  • 64,Charquet D,Senvat J,Marcon,J P,et al.Influence of Sulfur Content on the Thermal Creep of Zirconium Alloy Tubes at 400℃ .Journal of Nuclear Materials,255(1998):78~ 82.
  • 75,Mardon J P,Charquet D.Senvat J.Influence of Composition and Fabrication Process on Out of Pile and In Pile Properties of M5 Alloy.Twelfth International.Symposium on Zirconium in the Nuclear Industry,ASTM STP 1354,Toronto,Ontario,Canada.1998.
  • 8赵文金,周邦新.Zr_(-4)合金中第二相的研究[J].核动力工程,1991,12(5):67-72. 被引量:16

共引文献61

同被引文献4

  • 1Nuclear Engineering Fundamentals. Handbook ofnuclear engineering[M]. USA: Springer ScienceBusiness Media? 2010.
  • 2PUSA M, LEPPANEN J. Solving linear systemswith sparse Gaussian elimination in the Cheby-shev rational approximation method[J]. NuclearScience and Engineering, 2013,175 : 250-258.
  • 3FORREST R A. FISPACT-2007 : User manual[M]. UK: EURATOM/UKAEA Fusion Asso-ciation, Culham Science Centre,2007.
  • 4邱军,赵文金,Thomas Guilbert,Jean-Luc Bechade.3种锆合金的高温氧化行为[J].金属学报,2011,47(9):1216-1220. 被引量:15

引证文献1

二级引证文献2

相关作者

内容加载中请稍等...

相关机构

内容加载中请稍等...

相关主题

内容加载中请稍等...

浏览历史

内容加载中请稍等...
;
使用帮助 返回顶部