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加速器驱动次临界系统核数据库ANDL-ADS的研发和初步测试

Development and preliminary test of date library ANDL-ADS for accelerator-driven systems
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摘要 在加速器驱动次临界系统(Accelerator Driven Sub-critical Systems,ADS)中,散裂源中子能量可以到达上百Me V甚至Ge V,能谱分布非常复杂,已有的工作核数据库的截面数据无法满足其设计要求。传统工作核数据库的制作方法人工操作干预过多、耗时、繁琐且易出错,为此,开发出自动生成数据库程序。该程序在设计的能群结构、权重函数等参数基础上,通过程序自动生成适用于ADS系统的点状ACE格式和471群MATXS格式核数据库ANDL-ADS(Auto-generated Nuclear Date Library for ADS),支持高能中子(能量上限为150 Me V/200 Me V)的截面制作,并可根据需求进行多温截面的制作。通过不同材料的临界球、积分泄露率、高能屏蔽等基准例题的测试,初步验证了ANDL-ADS数据库的可靠性。 [Background] In the accelerator driven sub-critical systems(ADS), the energy of spallation neutron source can reach hundreds of Me V or even Ge V, and the distribution of energy spectrum is very complex. The existing working nuclear date libraries cannot meet its calculation requirements. The traditional methods of creating nuclear library are too much artificial intervention, time-consuming, cumbersome and error-prone. [Purpose] The study aims to develop a nuclear data library that satisfies the requirements of ADS systems design and analysis. [Methods] A multi-temperature library automatic generation program was developed to auto-generate a neutronnuclear date library ANDL-ADS(Auto-generated Nuclear Date Library for ADS) in both the point-wise date ACE format and the 471-group MATXS format according to the preset parameters. [Results] The reliability of ANDL-ADS is preliminarily verified by testing benchmark examples of criticality, leakage integral and high energy shielding. [Conclusion] Preliminary tests have been carried out on ANDL-ADS. Further benchmark tests and comprehensive applications are required to verify the reliability of cross sectional data fully.
出处 《核技术》 CAS CSCD 北大核心 2018年第3期61-66,共6页 Nuclear Techniques
基金 安徽省自然科学基金面上项目(No.1708085MA23)资助~~
关键词 加速器驱动次临界系统 自动生成 核数据库 临界 屏蔽 验证 ADS Automatic generation Nuclear library Criticality Shield Validation
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  • 1[1]Slessarev I. ,Tchistiakov A. IAEA ADS-BENCHMARK Results and Analysis[A]. TCM-Meeting, Madrid, 17-19September 1997.
  • 2[2]Briesmeister J F. MCNP-A general Monte Carlo N par ticle transport code [M]. LA-12625-M, Version 4B.New Mexico,Los Alamos National Laboratory, 1997.
  • 3[3]Allen G. Croff. Origen2: A Versatile Computer Code for Calculating the Nuclide Compositions and Characteristics of Nuclear Materials. 1982
  • 4[4]Kamil Tucek,Jan Wallenius,Waclaw Gudowski and Adam Soltan. IAEA Acceletor Driven System Neutronic Benchmark[A],TCM-Meeting, 1997
  • 5[5]Williams. Charlton, Comparisons of Helios,Origen2 and Monteburns Calculated 241 Am and 243 Am Concentration to Measured Values for PWR, BWR, and VVER spent fuel[J]. Journal of Nuclear Science and Technology,Vol. 37(1)NO7,2000.
  • 6马纪敏,刘永康,李茂生.次临界能源堆用多群截面库的研制与校验[J].核动力工程,2012,33(5):16-21. 被引量:3
  • 7李满仓,王侃,姚栋.基于连续能量蒙特卡罗方法的均匀化群常数计算[J].核科学与工程,2012,32(4):306-314. 被引量:4
  • 8刘萍.WIMS多群截面库更新时NJOY输入参数研究[J].原子核物理评论,2001,18(3):188-191. 被引量:2

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