吴宜灿,邹俊,郝丽娟,王明煌,杨琪,宋婧,汪进,尚雷明,龙鹏程,王芳,胡丽琴,何桃,FDS团队

• 1:中国科学院核能安全技术研究所中子输运理论与辐射安全重点实验室

摘要(Abstract)：

FDS团队结合聚变堆、先进裂变堆、聚变驱动次临界堆、加速器驱动次临界堆等核能系统对应用核数据的需求,设计开发出混合评价核数据库HENDL。HENDL包括输运核数据库、嬗变与活化核数据库、辐照损伤核数据库等,并针对先进核能系统的物理特点,从能量自屏效应、热散射效应、温度多普勒效应等方面进行了精确的截面修正。HENDL已通过国际基准模型与实验的验证与确认,并在ADSCLEAR、FDS-SFB为代表的重大核工程与核能研究中得到了广泛应用。

关键词(KeyWords)： 先进核能系统;多群数据库;基准检验

Abstract:

Keywords:

基金项目(Foundation): 国家自然科学基金(11405204、11305205、10675123),国家自然科学基金(11405204、11305205、10675123);; 中国科学院战略先导专项(XDA03040000),中国科学院信息化专项(XXH12504-1-09);; 国家ITER 973计划(2014GB112001);; 产业化基金

作者(Author): 吴宜灿,邹俊,郝丽娟,王明煌,杨琪,宋婧,汪进,尚雷明,龙鹏程,王芳,胡丽琴,何桃,FDS团队

参考文献(References)：

• [1]Otuka N,Dupont E,Semkova V,et al.Towards a more complete and accurate experimental nuclear reaction data library(EXFOR)[J].Nuclear Data Sheets,2014,120:272-276.
• [2]Chadwick M B,Herman M,et al.ENDF/B-VII.0:Next generation evaluated nuclear data library for nuclear science and technology[J].Nuclear data sheets,2006,107(12):2931-3060.
• [3]Santamarina A,Bernard D,Blaise P,et al.The JEFF-3.1.1nuclear data library[R].JEFF report,2009.
• [4]Lemmel H D,McLaughlin P K.BROND-2.2Russian evaluated neutron reaction data library[R].International Atomic Energy Agency,1994.
• [5]Shibata K,Kawano T,Nakagawa T,et al.Japanese evaluated nuclear data library version 3 revision-3:JENDL-3.3[J].Journal of Nuclear Science and Technology,2002,39:1125-1136.
• [6]Ge Z G,Yu H W,Zhuang Y X,et al.The updated version of the Chinese evaluated nuclear data Library(CENDL-3.1)and China nuclear data evaluation activities[J].EDP Sciences,2007,753-757.
• [7]D.López Aldama,F.Leszczynski,A.Trkov.WIMSD-D Library Update[R].Document INDC(NDS)-467.International Atomic Energy Agency,2003.
• [8]D.López Aldama,et al.FENDL2.1-Update of an evaluated nuclear data library for fusion applications[R].Document INDC(NDS)-467.International Atomic Energy Agency,2004.
• [9]D.López Aldama,et al.ADS-2.0---A Test Library for Accelerator Driven Systems and New Reactor Designs[R].Document INDC(NDS)-0545.International Atomic Energy Agency,2008.
• [10]M.B.Chadwick,et al.,LA150of Cross Sections,Heating,and Damage:A(Incident Neutrons)and Part B(Incident Protons),Nuclear Science and Engineering,293,131,1999.
• [11]Y.Watanabe,K.Kosako,S.Kunieda,et al,Status of JENDL High Energy File,Journal of the Korean Physical Society,59:1040-1045,2011.
• [12]Y Wu,U.Fischer.Integral Data Tests of the FENDL-1,EFF-2,EFF-3and JENDL-FF Fusion Nuclear Data Libraries[R].Forschungszentrum Karlsruhe,Technik and Umwelt Wissenschaftliche Berichte FZKA 5953,Februar 1998.
• [13]Yican Wu,Yixue Chen,U.Fischer,et al.Integral Data Tests of FENDL-2Fusion Nuclear Data Library with Neutronic Integral Experiments,Journal of Nuclear Science and Technology,supplement 1(March2000).
• [14]Gao Chunjing,Xu Dezheng,Li Jingjing,et al.Integral Data Test of HENDL1.0/MG and VisualBUS with Neutronics Shielding Experiments(I)[J].Wu Yican,Deng Tieru.Plasma Science and Technology,2004,6(5):2507-2513.
• [15]Gao Chunjing,Xu Dezheng,Li Jingjing,et al.Integral Data Test of HENDLl.0/MG with Neutronics Shielding Experiments(II)[J].Plasma Science and Technology,2004,6(6):2596-2600.
• [16]Dezheng Xu,Zhaozhong He,Jun Zou,et al.Production and testing of HENDL-2.1/CG coarsegroup cross-section library based on ENDF/B-VII.0[J],Fusion Engineering and Design,85(2010):2105-2110.
• [17]Jun Zou,Qin Zeng,Dezheng Xu,et al.Design and Production of Fine-group Cross Section Library HENDL3.0/FG Subcritical System[J],International Conference on the Physics of Reactors 2012,PHYSR2012:Advances in Reactor Physics,v5,p 5483-5490,2012.
• [18]Jun Zou,Qin Zeng,Chong Chen,et al,Development and Application of HENDL-ADS/MG Cross Section Library for ADS System[J],Transactions-American Nuclear Society;108;883-886(2013).
• [19]Hanshaw Heath L,et al.Estimation of the Effects of Self-Shielding on Multigroup Reactor Vessel Fluence Calculation[J],Trans.Am.Nucl.Soc,71:386-388,1994.
• [20]R.E.MacFarlane,et al.The NJOY Nuclear Data Processing System Version 91[R].LA-12740-M,Los Alamos National Laboratory,1994.
• [21]邹俊,用于次临界堆设计分析的核数据库系统研发与应用,博士,中国科学院等离子体物理研究所,2010.
• [22]P.Batistoni,L.Petrizzi,Task T426-Neutronics Experiments,Experimental Validation of Shut Down Dose Rates,EFF-Doc-726,March 2000.
• [23]K.Nishihara,T.Sugawara,H.Iwamoto,et al.Investigation of Nuclear Data Accuracy for the Accelerator-Driven System with Minor Actinide Fuel,OECD/NEA 11th Information Exchange Meeting,San Francisco(2010)315.
• [24]Sugawara T,Zolbadral T,Nishihara K,et al.Accelerator-Driven System Analysis by Using Different Nuclear Data Libraries[J].Atom Indonesia,2013,38(2).
• [25]Y.Wu,FDS Team.Conceptual Design Activities of FDS Series Fusion Power Plants in China.Fusion Engineering and Design,2006,81(23-24):2713-2718.
• [26]L.Qiu,Y.Wu,B.Xiao,et al.A Low Aspect Ratio Tokamak Transmutation System.Nuclear Fusion,2000,40:629-633.
• [27]Y.Wu,J.Qian,J.Yu.The Fusion-Driven Hybrid System and Its Material Selection.Journal of Nuclear Materials,2002,307-311:1629-1636.
• [28]Y.Wu,J.Jiang,M.Wang,et al.A Fusion-Driven Subcritical System Concept Based on Viable Technologies.Nuclear Fusion,2011,51(10):103036.
• [29]Y.Wu,FDS Team.Conceptual Design of the China Fusion Power Plant FDS-II.Fusion Engineering and Design,2008,83(10-12):1683-1689.
• [30]Y.Wu,FDS Team.Fusion-Based Hydrogen Production Reactor and Its Material Selection.Journal of Nuclear Materials,2009,386-388:122-126.
• [31]Y.Wu,Y.Bai,W.Wang,et.al,“Overview of China Lead Alloy cooled Reactor development and ADSProgram in China”,NUTHOS-9,Kaohsiung,Taiwan,September 9-13,2012.
• [32]吴宜灿,柏云清,宋勇等.中国铅基研究反应堆概念设计研究[J].核科学与工程,2014,34(2):201-208.
• [33]Y.Wu,J.Li,Y.Li,et al.,An integrated multifunctional neutronics calculation and analysis code system:VisualBUS,Chinese Journal of Nuclear Science and Engineering,27(2007)365-373.
• [34]Yican Wu,X.George Xu,The Need for Further Development of CAD/MCNP Interface Codes,Invited presentation at the American Nuclear Society Annual Meeting,Transactions of American Nuclear Society,2007,96:TRANSAO 961-882,ISSN:0003-018X,June 24-28,2007,Boston,Massachusetts.
• [35]Y.Wu,FDS Team,CAD-based Interface Programs for Fusion Neutron Transport Simulation.Fusion Engineering and Design,2009,84:1987-1992.
• [36]Y.Li,L.Lu,A.Ding,et al.Benchmarking of MCAM 4.0 with the ITER 3D model,Fusion Engineering and Design 82(2007)2861-2866.Also presented at the 24th Symposium on Fusion Technology(SOFT-24),Warsaw,Sep.11-15,2006.
• [37]Y.Wu,Z.Xie,U.Fischer.A Discrete Ordinates Nodal Method for One-Dimensional Neutron Transport Calculation in Curvilinear Geometries.Nuclear Science and Engineering,1999,133(3):350-357.
• [38]Y.Wu,J.Song,H.Q.Zheng,et al.CAD-based Monte Carlo Program for Integrated Simulation of Nuclear System SuperMC.Annals of Nuclear Energy,DOI:10.1016/j.anucene.2014.08.058.
• [39]J.Song,G.Y.Sun,Z.P.Chen,et al.Benchmarking of CAD-based SuperMC with ITER Benchmark Model.Fusion Engineering and Design,DOI:10.1016/j.fusengdes.2014.05.003.
• [40]王明煌,次临界乏燃料焚烧堆中子学设计研究,博士,中国科学技术大学,2012.
• [41]Qi Yang,Bin Li,Chao Chen,et al.Radiation Shielding Design and Analysis for CLEAR-I[J],Paper No.ICONE21-15995,pp.V001T04A022;5pages.
• [42]Bin Li,Qi Yang,Jou Zou,et al.Shielding design and analysis for the proton tube of China LEAD-ALLOYCooled Reasearch Reactor(CLEAR-I),Paper No.ICONE21-15763,pp.V001T04A020;5pages.