Implementation and assessment of a stability-enhancing and high-resolution numerical scheme in RELAP5

Wei LI; Guanghui SU; Suizheng QIU; Wenxi TIAN; Ping CHEN; Yuanming LI

doi:10.11889/j.0253-3219.2016.hjs.39.110601

您当前的位置：

首页 >

文章列表页 >

Implementation and assessment of a stability-enhancing and high-resolution numerical scheme in RELAP5

NUCLEAR ENERGY SCIENCE AND ENGINEERING | 更新时间：2021-05-24

- Implementation and assessment of a stability-enhancing and high-resolution numerical scheme in RELAP5
- NUCLEAR TECHNIQUES Vol. 39, Issue 11, Article number: 110601(2016)
- 作者机构：
  
  1.中国核动力研究设计院核反应堆系统设计技术重点实验室成都 610213
  2.西安交通大学核科学与技术学院西安 710049
- 作者简介：
- 基金信息：
- DOI：10.11889/j.0253-3219.2016.hjs.39.110601
  CLC： TL33
- Received：30 May 2016，
  
  Revised：01 September 2016，
  
  Published：2016-11
- 稿件说明：
移动端阅览
Wei LI, Guanghui SU, Suizheng QIU, et al. Implementation and assessment of a stability-enhancing and high-resolution numerical scheme in RELAP5[J]. Nuclear techniques, 2016, 39(11): 110601
DOI：

Wei LI, Guanghui SU, Suizheng QIU, et al. Implementation and assessment of a stability-enhancing and high-resolution numerical scheme in RELAP5[J]. Nuclear techniques, 2016, 39(11): 110601 DOI： 10.11889/j.0253-3219.2016.hjs.39.110601.

摘要

在计算稳定性的改进方面，修正RELAP5程序中的虚拟质量力（Virtual mass force）形式，同时添加了新的界面压力项（Interface pressure）；在计算精度的改进方面，采用具有总变差减小（Total variation diminish，TVD）特点的高精度通量限制器（Flux limiter）方法取代RELAP5程序原本的一阶迎风方法来离散质量和能量守恒方程中的对流项。在模拟水平管道内空泡份额微扰随时间发展的数值实验中，相比改进前的RELAP5，改进后的RELAP5计算得到的微扰幅度并未增长；在模拟液相沉降的数值实验中，改进前的RELAP5程序计算得到了不真实的空泡份额分布，而改进后的RELAP5在不同的网格数量下能够得到收敛的稳定解。对Ransom水龙头数值实验和Marviken CFT 15大破口喷放实验的计算表明，改进后的具有二阶TVD格式的RELAP5程序能够得到更接近实验数据的计算结果。

Abstract

Background

RELAP5 has been widely used in the field of nuclear thermal-hydraulics and safety analysis. However

improvement issues in terms of numerical stability and accuracy exist due to its basic single-pressure two-fluid model.

Purpose

This study aims to enhance the numerical stability and numerical accuracy of RELAP5 by modifying the mathematical structure of RELAP5 basic model.

Methods

Firstly

the default mathematical expression of the virtual mass force was modified in the RELAP5 code. Secondly

an interface pressure term was incorporated in the code

and a total variation diminish (TVD)-type flux limiter method was implemented in the RELAP5 code in place of the default 1st-order upwind scheme for the convective terms in mass and energy conversation equations.

Results

In a numerical test where the evolvements of void fraction perturbation were concerned

the modified RELAP5 predicted no growth of the perturbation amplitude in contrast to a rapidly developing divergence for the default RELAP5. In addition

for the phase segmentation problem

convergence was accomplished on finer mesh by the modified RELAP5

while non-physical distribution of the void fraction was rendered by the default RELAP5 especially for finer mesh. When applied to the Ransom water faucet numerical test and Marviken CFT 15 experiments

the improved RELAP5 with 2nd-order of accuracy was more reliable in that the predictions were closer to the experimental results.

Conclusion

Compared with the original RELAP5

the modified or improved RELAP5 showed evident numerical stability and accuracy during the assessment in this work.

关键词

Keywords

references

L Ge , H T Wang , G L Zhang , . Thermal-hydraulic design and transient analysis of passive cooling system for CPR1000 spent fuel storage pool . Nuclear Science and Techniques , 2016 . 27 ( 1 ): 8 DOI: 10.1007/s41365-016-0017-6 http://doi.org/10.1007/s41365-016-0017-6 .

R W Lyczkowski , D Gidaspow , C W Solbrig , . Characteristics and stability analyses of transient one-dimensional two-phase flow equations and their finite difference approximations . Nuclear Science and Engineering , 1978 . 66 ( 3 ): 378 - 396 . DOI: 10.13182/NSE78-4 http://doi.org/10.13182/NSE78-4 .

P D Lax . On the nation of hyperbolicity . Communications on Pure and Applied Mathematics , 1980 . 33 ( 3 ): 395 - 397 . DOI: 10.1002/cpa.3160330309 http://doi.org/10.1002/cpa.3160330309 .

D Wang , J H Mahaffy , J Staudenmeier , . Implementation and assessment of high-resolution numerical methods in TRACE . Nuclear Engineering and Design , 2013 . 263 ( 0 ): 327 - 341 . DOI: 10.1016/j.nucengdes.2013.05.015 http://doi.org/10.1016/j.nucengdes.2013.05.015 .

张小英 , 丁斐 , 陈佳跃 . 反应堆一维两流体模型二阶精度数值解法研究 . 核动力工程 , 2013 . 34 ( 4 ): 27 - 32 .

Xiaoying ZHANG , Fei DING , Jiayue CHEN . Study on numerical solution of the two dimensional two fluid model of the reactor . Nuclear Power Engineering , 2013 . 34 ( 4 ): 27 - 32 . DOI: 10.3969/j.issn.0258-0926.2013.04.007DOI:10.3969/j.issn.0258-0926.2013.04.007 http://doi.org/10.3969/j.issn.0258-0926.2013.04.007DOI:10.3969/j.issn.0258-0926.2013.04.007 .

D Drew , L Cheng , R Lahey . The analysis of virtual mass effects in two-phase flow . International Journal of Multiphase Flow , 1979 . 5 ( 4 ): 233 - 242 . DOI: 10.1016/0301-9322(79)90023-5 http://doi.org/10.1016/0301-9322(79)90023-5 .

I Tiselj , S Petelin . Modelling of two-phase flow with second-order accurate scheme . Journal of Computational Physics , 1997 . 136 ( 2 ): 503 - 521 . DOI: 10.1006/jcph.1997.5778 http://doi.org/10.1006/jcph.1997.5778 .

L Hogon , U Lee , K Kim , . Application of hyperbolic two-fluids equations to reactor safety code . Nuclear Engineering and Technology , 2003 . 35 ( 1 ): 45 - 54 . http://cn.bing.com/academic/profile?id=1577674790&encoded=0&v=paper_preview&mkt=zh-cn .

RELAP5 Code Development Team. RELAP5/MOD3 code manual Vol I:code structure, system models, and solution methods[R]. Idaho Falls:Idaho National Laboratory, 2001

H K Versteeg , W Malalasekera . An introduction to computational fluid dynamics:the finite volume method , : Essex, UK Pearson Education , 2007 .

N P Waterson , H Deconinck . Design principles for bounded higher-order convection schemes-a unified approach . Journal of Computational Physics , 2007 . 224 ( 1 ): 182 - 207 . DOI: 10.1016/j.jcp.2007.01.021 http://doi.org/10.1016/j.jcp.2007.01.021 .

Ransom V. Numerical benchmark tests[A]. Hewitt G, Delhay J, Zuber N. Multiphase science and technology[M]. Washington DC:Hemisphere Publishing Corporation, 1987

Kim K, Kim H J. Assessment of RELAP5/MOD 2 critical flow model using Marviken test data 15 and 24[R]. Washington, DC:Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1992

Views

下载量

CSCD

Alert me when the article has been cited

提交

Tools

Publicity Resources

Applicability of secondary-developed RELAP5 code for PRS operation analysis under inclined conditions

Development and analysis of passive residual heat-removal system on secondary side of small reactor

Development and validation of real-time modeling and simulation platform for molten salt reactor based on EPICS framework

Development of a SiPM-based practical plastic scintillation fiber dosimeter

Preparation of liquid scintillation sample for lithium carbonate pellet for tritium production rate measurement

Related Author

HAO Chengming

ZHAO Jing

WANG Tao

LIANG Tiebo

WANG Yu

XU Huitian

SUN Yan

YU Qiao

Related Institution

No. Unit of PLA

Nuclear Power Institute of China

School of Mechanical Engineering, Shanghai Jiao Tong University

College of Smart Energy, Shanghai Jiao Tong University

ShanghaiTech University

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