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Burnup information updating and verification based on WIMS-D library
- NUCLEAR TECHNIQUES Vol. 40, Issue 11, Article number: 110602(2017)
- 作者机构：
1.华北电力大学 核科学与工程学院 北京 102206
2.国家核电技术有限公司 北京软件技术中心 北京 100029
3.中国科学院核能安全技术研究所 合肥 230000
- 作者简介：
- 基金信息：National Natural Science Foundation of China;National Research and Development Projects;Fundamental Research Funds for the Central Universities
DOI：10.11889/j.0253-3219.2017.hjs.40.110602
CLC： TL99Received：28 March 2017，
Revised：12 May 2017，
Published：10 November 2017
- 稿件说明：
移动端阅览
Xiang XIAO, Jun WU, You GONG, et al. Burnup information updating and verification based on WIMS-D library[J]. Nuclear techniques, 2017, 40(11): 110602
Xiang XIAO, Jun WU, You GONG, et al. Burnup information updating and verification based on WIMS-D library[J]. Nuclear techniques, 2017, 40(11): 110602 DOI： 10.11889/j.0253-3219.2017.hjs.40.110602.
摘要
随着AP1000等新一代压水堆的发展，燃耗深度在不断提高，平均卸料燃耗深度提高到60 GW d·t
-1
。然而，传统使用的WIMS69群和XMAS172群WIMS-D格式多群常数库，其能群结构存在共振峰重叠，核素种类较少，裂变产物产额的偏差较大，并且伪裂变产物中包含的核素种类较多而导致
152
Gd、
160
Gd、
159
Tb、
160
Tb等重要核素无法得到精确处理等问题。因此，本文主要针对AP1000等新一代反应堆的设计以及运行特点，基于ENDF/B-Ⅶ.1库，并且在现有基础上针对WIMS-D库中的伪裂变产物、裂变产物燃耗链以及裂变产物产额等燃耗数据进行更新，再通过NJOY程序开发了SHEM281群WIMS-D格式多群常数库。通过DRAGON程序挂载该WIMSD281库，对其进行临界和燃耗两方面基准验证。计算结果表明，该数据库的计算结果与基准值符合较好，精度较高，结果可靠，可初步用于压水堆的相关计算。
Abstract
Background
2
With the development of AP1000
the burnup has been raised constantly and the average burnup is expected to reach 60 GW d·t
-1
. However
the traditional WIMS-D library which is based on WIMS69 and XMAS172 energy group structure
has too many flaws such as the resonance overlap effect
lack of some nuclides
unreliable value of the fission product yield and thus can't explicitly treat the nuclide of
152
Gd
160
Gd
159
Tb and
160
Tb in the pseudo fission product.
Purpose
2
A new version of WIMS-D library based on ENDF/B-Ⅶ.1 with SHEM281 group structure is developed to improve the accuracy of cell calculation using the NJOY program.
Methods
2
The new library is verified through the analysis of criticality and burnup benchmarks by using DRAGON program.
Results
2
The results show that the calculation values are in good agreement with the benchmark.
Conclusion
2
The new library has high precision and the result is reliable
which can be used for the PWR's calculation.
关键词
Keywords
references
DAN G C, Robert C B, Yaron D, et al . Handbook of nuclear engineering:Vol.1:nuclear engineering fundamentals; Vol.2:reactor design; Vol.3:reactor analysis; Vol.4:reactors of generations Ⅲ and Ⅳ; Vol.5:fuel cycles, decommissioning, waste disposal and safeguards[M]. Springer, 2010
A Santamarina , N Hfaiedh , R Letellier , . Advanced neutronics tools for BWR design calculations . Nuclear Engineering and Design , 2008 . 238 ( 8 ): 1965 - 1974 . DOI: 10.1016/j.nucengdes.2007.12.012 http://doi.org/10.1016/j.nucengdes.2007.12.012 .
Aldama D L, Leszczynski F, Trkov A. WIMS-D library update[R]. Final Report of a Co-ordinate Research Project, 2003
Macfarlane R E. A code system for producing pointwise and multigroup neutron and photon cross sections from ENDF/B evaluated nuclear data[R]. Los Alamos, New Mexico:Los Alamos National Laboratory, USA Report PSR-171, 1987
Z Dong , J Wu , X Ma , . Development and verification of a 281-group WIMS-D library based on ENDF/B-Ⅶ . Annals of Nuclear Energy , 2016 . 91 189 - 194 . DOI: 10.1016/j.anucene.2016.01.014 http://doi.org/10.1016/j.anucene.2016.01.014 .
Marleau G, Hébert A, Roy R. A user guide for DRAGON 3.06[R]. Report IGE-174 Rev, 2008:7
A Trkov , D L Aldama . Definition of pseudo fission product data for reactor calculations . Nuclear Energy in Central Europe , 1999 . 99 57 - 62 . https://www.oecd-nea.org/science/docs/pubs/hprl.pdf .
杨 伟焱 , 毕 光文 , 杨 波 , . 低价值控制棒中子吸收体材料燃耗相关数据的制作及验证研究 . 核科学与工程 , 2014 . ( 3 ): 369 - 376 . http://www.cnki.com.cn/Article/CJFDTOTAL-HKXY201403015.htm .
Weiyan YANG , Guangwen BI , Bo YANG , . Study on production and validation of low worth control rod material burnup calculation parameters . Nuclear Science and Engineering , 2014 . ( 3 ): 369 - 376 . http://www.cnki.com.cn/Article/CJFDTOTAL-HKXY201403015.htm .
胡 也 , 陈 义学 , 杨 寿海 , . 基于Monte Carlo方法的压水堆相关组件内热源计算与分析 . 核科学与工程 , 2013 . 33 ( 2 ): 168 - 174 . http://www.cnki.com.cn/Article/CJFDTOTAL-HKXY201302010.htm .
Ye HU , Yixue CHEN , Shouhai YANG , . Calculation and analysis of heat sour of PWR assemblies based on Monte Carlo method . Nuclear Science and Engineering , 2013 . 33 ( 2 ): 168 - 174 . http://www.cnki.com.cn/Article/CJFDTOTAL-HKXY201302010.htm .
A Trkov . Processing of the fission product yield and decay data . Nuclear Energy in Central Europe , 1999 . 99 57 - 62 . http://www-rsicc.ornl.gov/newsletters/news.02/news02apr.pdf .
曹 博 , 陈 义学 , 李 晓静 , . AP1000典型燃料组件物理特性初步分析 . 原子能科学技术 , 2013 . 47 ( 增2 ): 599 - 602 . DOI: 10.7538/yzk.2013.47.S1.0599 http://doi.org/10.7538/yzk.2013.47.S1.0599 .
Bo CAO , Yixue CHEN , Xiaojing LI , . Physical characteristics preliminary analysis on AP1000 fuel assembly . Atomic Energy Science and Technology , 2013 . 47 ( Suppl 2 ): 599 - 602 . DOI: 10.7538/yzk.2013.47.S1.0599 http://doi.org/10.7538/yzk.2013.47.S1.0599 .
F B Brown . MCNP-a general Monte Carlo N-particle transport code , : Version 5.Oak Ridge, TN Los Alamos National Laboratory , 2003 .
谢 仲生 , 尹 邦华 , 潘 国品 . 核反应堆物理分析 , : 北京 原子能出版社 , 1996 .
Zhongsheng XIE , Banghua YIN , Guopin PAN . The analysis of nuclear reactor physics , : Beijing Atomic Energy Science and Technology , 1996 .
Leszczynski F. NRSC system, user's manual[R]. Internal Report CAB-CNEA, 1999
Bucholz J A. SCALE:a modular code system for performing standardized computer analyses for licensing evaluation[R]. TN, USA:Oak Ridge National Laboratory, 1982
马 续波 , 鲁 凡 , 陈 义学 , . 基于cosRMC的新一代PWR栅元和组件燃耗计算 . 原子能科学技术 , 2016 . 50 ( 11 ): 2010 - 2017 . DOI: 10.7538/yzk.2016.50.11.2010 http://doi.org/10.7538/yzk.2016.50.11.2010 .
Xubo MA , Fan LU , Yixue CHEN , . Burnup calculation of next generation PWR cell and assembly based on cosRMC . Atomic Energy Science and Technology , 2016 . 50 ( 11 ): 2010 - 2017 . DOI: 10.7538/yzk.2016.50.11.2010 http://doi.org/10.7538/yzk.2016.50.11.2010 .
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