Research and verification of Monte Carlo burnup calculations based on Chebyshev rational approximation method

Wending FAN; Guangyao SUN; Binhang ZHANG; Rui CHEN; Lijuan HAO

doi:10.11889/j.0253-3219.2016.hjs.39.040501

您当前的位置：

首页 >

文章列表页 >

Research and verification of Monte Carlo burnup calculations based on Chebyshev rational approximation method

更新时间：2021-05-25

- Research and verification of Monte Carlo burnup calculations based on Chebyshev rational approximation method
- NUCLEAR TECHNIQUES Vol. 39, Issue 4, Article number: 040501(2016)
- 作者机构：
  
  1.中国科学技术大学核科学技术学院合肥 230027;
  2.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合肥 230031
- 作者简介：
- 基金信息：
- DOI：10.11889/j.0253-3219.2016.hjs.39.040501
  CLC： TL329.2
- Received：30 November 2015，
  
  Accepted：2016-03-08，
  
  Published：25 January 2016
- 稿件说明：
移动端阅览
Wending FAN, Guangyao SUN, Binhang ZHANG, et al. Research and verification of Monte Carlo burnup calculations based on Chebyshev rational approximation method[J]. Nuclear techniques, 2016, 39(4): 040501
DOI：

Wending FAN, Guangyao SUN, Binhang ZHANG, et al. Research and verification of Monte Carlo burnup calculations based on Chebyshev rational approximation method[J]. Nuclear techniques, 2016, 39(4): 040501 DOI： 10.11889/j.0253-3219.2016.hjs.39.040501.

摘要

燃耗计算在反应堆设计、分析研究中起着重要作用。相比于传统点燃耗算法

切比雪夫有理逼近方法(Chebyshev rational approximation method

CRAM)具有计算速度快、精度高的优点。基于超级蒙特卡罗核计算仿真软件系统SuperMC(Super Monte Carlo Simulation Program for Nuclear and Radiation Process)

采用切比雪夫有理逼近方法和桶排序能量查找方法

进行了蒙特卡罗燃耗计算的初步研究与验证。通过燃料棒燃耗例题以及IAEA-ADS(International Atomic Energy Agency-Accelerator Driven Systems)国际基准题

初步验证了该燃耗计算方法的正确性

且IAEA-ADS基准题测试表明

与统一能量网格方法相比

桶排序能量查找方法在保证了计算效率的同时减少了内存开销。

Abstract

Background:

Burnup calculation is the key point of reactor design and analysis. It's significant to calculate the burnup situation and isotopic atom density accurately while a reactor is being designed.

Purpose:

Based on the Monte Carlo particle simulation code SuperMC(Super Monte Carlo Simulation Program for Nuclear and Radiation Process)

this paper aimed to conduct preliminary study and verification on Monte Carlo burnup calculations.

Methods:

For the characteristics of accuracy

this paper adopted Chebyshev rational approximation method(CRAM) as the point-burnup algorithm. Moreover

instead of the union energy grids method

this paper adopted an energy searching method based on bucket sort algorithm

which reduced the memory overhead on the condition that the calculation efficiency is ensured.

Results:

By calculating the fuel rod burnup problem and the IAEA-ADS(International Atomic Energy Agency-Accelerator Driven Systems) international benchmark

the simulation results were basically consistent with Serpent and other counties' results

respectively. In addition

the bucket sort energy searching method reduced about 95% storage space compared with union energy grids method for IAEA-ADS benchmark.

Conclusion:

Depending on these results

the correctness of burnup calculations method implemented by this paper has been verified.

关键词

Keywords

references

李静惊 , 陈明亮 , 郑善良 , . 基于离散纵坐标输运计算方法的三维燃耗程序发展研究 . 核科学与工程 , 2007 . 27 ( 4 ): 379 - 384 .

LI Jingjing , CHEN Mingliang , ZHENG Shanliang , . Development of three-dimensional burnup code system based on discrete ordinates(SN) transport method . Nuclear Science and Engineering , 2007 . 27 ( 4 ): 379 - 384 .

Wu Y , Zheng S , Zhu X , . Conceptual design of the fusion-driven subcritical system FDS-I . Fusion Engineering and Design , 2006 .

Wu Y , FDS Team . Conceptual design of the China fusion power plant FDS-Ⅱ . Fusion Engineering and Design , 2008 . 83 ( 1 ): 1683 - 1689 .

Wu Y , Jiang J , Wang M , . A fusion-driven subcritical system concept based on viable technologies . Nuclear Fusion , 2011 . 51 ( 10 ): 103036 .

Qiu L , Wu Y , Xiao B , . A low aspect ratio Tokamak transmutation system . Nuclear Fusion , 2000 . 40 ( 3Y ): 629 - 633 .

佘顶 , 王侃 , 余纲林 . 堆用蒙卡程序燃耗计算功能开发 . 核动力工程 , 2012 . 33 ( 3 ): 1 - 5 .

SHE Ding , WANG Kan , YU Ganglin . Development of burnup calculation function in reactor Monte Carlo code RMC . Nuclear Power Engineering , 2012 . 33 ( 3 ): 1 - 5 .

Briesmeister J F . MCNP-a general Monte Carlo N-particle transport code . Version 5. USA:Los Alamos National Laboratory , 2003 .

Croff A G . A user's manual for ORIGEN2 computer code . Oak Ridge National Laboratory , 1980 .

Pusa M , Leppänen J . Computing the matrix exponential in burnup calculations . Nuclear Science and Engineering , 2010 . 164 ( 2 ): 140 - 150 .

Leppänen J . Two practical methods for unionized energy grid construction in continuous-energy Monte Carlo neutron transport calculation . Annals of Nuclear Energy , 2009 . 36 ( 7 ): 878 - 885 .

She D , Liu Y , Wang K , . Development of burnup methods and capabilities in Monte Carlo code RMC . Annals of Nuclear Energy , 2013 . 51 ( 1 ): 289 - 294 .

Wu Y , Song J , Zheng H , . CAD-based Monte Carlo program for integrated simulation of nuclear system SuperMC . Annals of Nuclear Energy , 2015 . 82 ( 1 ): 161 - 168 .

Song J , Sun G Y , Chen Z P , . Benchmarking of CAD-based SuperMC with ITER benchmark model . Fusion Engineering and Design , 2014 . 89 ( 1 ): 2499 - 2503 .

Chen Z P , Zheng H Q , Sun G Y , . Preliminary study on CAD-based method of characteristics for neutron transport calculation . Chinese Physics C , 2014 . 38 ( 5 ): 058201 .

孙光耀 , 宋婧 , 郑华庆 , . 超级蒙特卡罗计算软件SuperMC2.0中子输运计算校验 . 原子能科学与技术 , 2013 . 47 ( 增 ): 520 - 525 .

SUN Guangyao , SONG Jing , ZHENG Huaqing , . Benchmark of neutron transport simulation capability of super Monte Carlo calculation program SuperMC 2.0 . Atomic Energy Science and Technology , 2013 . 47 ( suppl ): 520 - 525 .

Wu Y , FDS Team . CAD-based interface programs for fusion neutron transport simulation . Fusion Engineering and Design , 2009 . 84 ( 7-11 ): 1987 - 1992 .

Wu Y , Xie Z , Fischer U . A discrete ordinates nodal method for one-dimensional neutron transport calculation in curvilinear geometries . Nuclear Science and Engineering , 1999 . 133 ( 3 ): 350 - 357 .

Hu H , Wu Y , Chen M , . Benchmarking of SNAM with the ITER 3D model . Fusion Engineering and Design , 2007 . 82 ( 1 ): 2867 - 2871 .

吴宜灿 , 何桃 , 胡丽琴 , . 核与辐射安全仿真系统SuperMC/RVIS 2.3研发与应用 . 原子能科学技术 , 2015 . 49 ( 增 ): 7 - 15 .

WU Yican , HE Tao , HU Liqin , . Development of virtual reality-based simulation system for nuclear and radiation safety . Atomic Energy Science and Technology , 2015 . 49 ( suppl ): 7 - 15 .

Wu Y , FDS Team . Conceptual design and testing strategy of a dual functional lithium-lead test blanket module in ITER and EAST . Nuclear Fusion , 2007 . 47 ( 11 ): 1533 - 1539 .

Wu Y , FDS Team . Design analysis of the China dual-functional lithium lead(DFLL) test blanket module in ITER . Fusion Engineering and Design , 2007 . 82 ( 1 ): 1893 - 1903 .

Wu Y , FDS Team . Conceptual design activities of FDS series fusion power plants in China . Fusion Engineering and Design , 2006 . 81 ( 1 ): 2713 - 2718 .

Isotalo A . Computational methods for burnup calculations with Monte Carlo neutronics . Finland:Aalto University , 2013 .

Fridman E , Shwageraus E , Galperin A . Efficient generation of one-group cross sections for coupled Monte Carlo depletion calculations . Nuclear Science and Engineering , 2008 . 159 ( 1 ): 37 - 47 .

Slessarev I , Tchistiakov A . IAEA ADS-benchmark results and analysis . Madrid:TCM-Meeting, September 17-19 , 1997 .

蒋校丰 , 谢仲生 . 蒙卡-燃耗程序系统及ADS基准题的计算 . 核科学与工程 , 2003 . 23 ( 4 ): 325 - 331 .

JIANG Xiaofeng , XIE Zhongsheng . Monte Carlo-burnup code system and it's application to IAEA ADS benchmark . Nuclear Science and Engineering , 2003 . 23 ( 4 ): 325 - 331 .

Views

下载量

CSCD

Alert me when the article has been cited

提交

Tools

Publicity Resources

Development of the neutronics calculation module of neutronics and thermal hydraulic calculation program NECP-Panda for pebble-bed high temperature gas-cooled reactor

Development and validation of LightAB: a new light general-purpose activation-burnup program

Calculation methods of parameters in α particle measurement

Preliminary analysis of nuclear criticality safety of micro-reactor under high-speed impact

Design of an ultra-high dose rate cell irradiation experimental platform using a medical proton linear injector

Related Author

WU Yuxuan

WANG Yongping

QIN Shuai

CAO Liangzhi

WU Hongchun

LUO Yong

LIU Langtao

PAN Qingquan

Related Institution

Huaneng Nuclear Energy Technology Research Institute

Xi'an Jiaotong University

School of Nuclear Science and Engineering, Shanghai Jiao Tong University

Nanhua University

Shanghai Institute of Applied Physics, Chinese Academy of Sciences

AI问答

Address：2019 Jialuo Road, Jiading, Shanghai, China Postal code：201800
Tel：021-39194977 Email：LHB@sinap.ac.cn
Technical support is provided by Beijing Founder electronics co., LTD 沪ICP备05005479号-1 京公网安备11010802024621
It is recommended to read the content of this site in Chrome&IE9+. Please switch to extreme mode in browser 360.
Cookies We use cookies to help provide and enhance our service and tailor content. By continuing, you agree to the use of cookies.
Total Visits：881268 Visits Today：795

⁰