板状燃料组件流量分配CFD研究与优化

doi:10.11889/j.0253-3219.2016.hjs.39.080603

Nuclear Techniques ›› 2016, Vol. 39 ›› Issue (8): 80603-080603.doi: 10.11889/j.0253-3219.2016.hjs.39.080603

• NUCLEAR ENERGY SCIENCE AND ENGINEERING • Previous Articles Next Articles

CFD investigation and optimization on flow distribution of plate-type assembly

DONG Huaping¹, FAN Wenyuan², GUO Yun²

1 Science and Technology on Reactor System Design Technology Laboratory, Nuclear Power Institute of China, Chengdu 610041, China;
2 School of Nuclear Science and Technology, University of Science and Technology of China, Hefei 230026, China

Received:2016-04-30 Revised:2016-06-30 Online:2016-08-10 Published:2016-08-15
Supported by:
Supported by Open Fund Project of Key Laboratory of Nuclear Reactor System Design Technology, China Nuclear Power Research and Design Institute (No.HT-CENT-02-2014001);National Nuclear Fusion Project (No.2013GB108004)

Abstract

Abstract:

Background: Plate-type assembly is widely used in research reactors. Flow distribution inside the assembly is a key factor in design process. Computational fluid dynamics (CFD) method is an important way for flow distribution calculations. However, huge requirements on computing resources limit the application scope of CFD method. Purpose: The aim is to invest the CFD method in the flow distribution with smaller requirements on computing resources. Methods: New developed CFD method by partial modeling and iterating is used. Results: Using the traditional CFD and newly developed method, flow distribution calculations are done toward plate-type assembly with and without the flow distributor, and the maximum differences are 0.81% and 0.56%, respectively. Conclusion: The partial modeling and iterating method could optimize CFD simulations on flow distribution of plate-type assembly accurately, economically and quickly.

Key words: Plate-type assembly, Flow distribution, CFD

CLC Number:

TL331

DONG Huaping, FAN Wenyuan, GUO Yun. CFD investigation and optimization on flow distribution of plate-type assembly[J].Nuclear Techniques, 2016, 39(8): 80603-080603.

References

1 李健全, 陈晓明, 李金才. 板状燃料堆芯流道阻塞事故分析[J]. 原子能科学技术, 2002, 36(1):76-79 LI Jianquan, CHEN Xiaoming, LI Jincai. Analysis on a flow blockage incident at a plate-type fuel reactor[J]. Atomic Energy Science and Technology, 2002, 36(1):76-79

2 宋磊.板状燃料组件堵流事故数值分析[D]. 哈尔滨:哈尔滨工程大学, 2013 SONG Lei. Numerical analysis of the flow of the plate fuel assembly[D]. Harbin:Harbin Engineering University, 2013

3 宋磊, 郭赟, 曾和义. 板状燃料组件入口堵流事故下流场和温度场的瞬态数值计算[J]. 核动力工程, 2014, 35(3):6-10 SONG Lei, GUO Yun, ZENG Heyi. Numerical analysis on transient flow and temperature field during inlet flow blockage accidents of plate-type fuel assembly[J]. Nuclear Power Engineering, 2014, 35(3):6-10

4 Fan W, Peng C, Guo Y. CFD study on inlet flow blockage accidents in rectangular fuel assembly[J]. Nuclear Engineering and Design, 2015, 292:177-186. DOI:10.1016/j.nucengdes.2015.06.016

5 Lu Q, Qiu S, Su H G. Development of a thermal-hydraulic analysis code for research reactors with plate fuels[J]. Annals of Nuclear Energy, 2009, 36(4):433-447. DOI:10.1016/j.anucene.2008.11.038

6 Lu Q, Qiu S, Su G H. Flow blockage analysis of a channel in a typical material test reactor core[J]. Nuclear Engineering and Design, 2009, 239(1):45-50. DOI:10.1016/j.nucengdes.2008.06.016

7 陈道龙, 姜琲. 高通量工程试验堆堆芯燃料元件温度-流量测量装置[J]. 核科学与工程, 1984, 4(6):178-181 CHEN Daolong, JIANG Bei. The in-core fuel element temperature-flow measurement facility of HFETR[J]. Chinese Journal of Nuclear Science and Engineering, 1984, 4(6):178-181

8 陈道龙, 姜琲. 高通量工程试验堆堆芯燃料元件温度和流量测量[J]. 中国核科技报告, 1988, (S2):1-28 CHEN Daolong, JIANG Bei. The in-core fuel element temperature and flow measurement facility of HFETR[J]. China Nuclear Science and Technology Report, 1988, (S2):1-28

9 Fan W, Peng C, Wang G, et al. CFD study on inlet flow blockage accidents in multi-layer annular flow channels[C]. ICONE23(Paper ID:1845), Japan, 2015

10 樊文远, 郭赟, 彭常宏. 多层环形流道阻塞事故三维数值分析初步探索[J]. 核动力工程, 2016, 37(1):123-128 FAN Wenyuan, GUO Yun, PENG Changhong. Preliminary 3D numerical study on flow blockage accident in multi-layer annular flow channels[J]. Nuclear Power Engineering, 2016, 37(1):123-128

11 Fan W, Peng C, Chen Y, et al. A new CFD modeling method for flow blockage accident investigations[J]. Nuclear Engineering and Design, 2016, 303:31-41. DOI:10.1016/j.nucengdes.2016.04.006

12 汪利民, 宗桂芳, 尹涛. 600MW反应堆堆芯入口流量分配实验研究[J]. 工程热物理学报, 1999, 20(2):185-189 WANG Limin, ZONG Guifang, YIN Tao. Test of flow distribution at the core in let of 600 MW reactor[J]. Journal of Engineering Thermophysics, 1999, 20(2):185-189

13 ANASYS. ANASYS FLUENT 12.0 theory guide[Z]. Canonsburg, PA, USA, 2009

[1]	Qingyuan LI,Bo XU,Chong ZHOU,Yang ZOU,Hongjie XU. The optimization of flow rate distribution design of 373 MW molten salt reactor-liquid fuel [J]. Nuclear Techniques, 2019, 42(7): 0-070605-10.
[2]	SHEN Hao, XIONG Jinbiao, CHENG Xu. Uncertainty quantification study of CFD on the rod bundle flow [J]. Nuclear Techniques, 2018, 41(3): 30601-030601.
[3]	YAO Jun, ZHANG Xisi, HU Wenjun, CHAI Xiang, YANG Yanhua. Effect of block parameter on fluid flow and heat transfer in LBE-cooled fast reactor under blockage accident [J]. Nuclear Techniques, 2018, 41(2): 20604-020604.
[4]	FENG Quansheng, XU Bo, PAN Deng, ZOU Yang, XU Hongjie. Thermal-hydraulics numerical analyses of molten salt pebble-bed reactor core inlet [J]. Nuclear Techniques, 2017, 40(9): 90601-090601.
[5]	CHEN Hui, ZENG Wenjie, ZHANG Dongnan, YU Tao. Analysis of jet device transient feature during start-up period of primary pump [J]. Nuclear Techniques, 2017, 40(5): 50602-050602.
[6]	MEI Mudan, LIN Dafu, CHEN Xingwei, YAN Rui, LI Minghai, ZOU Yang. Flow distribution plate design of molten salt reactor based on pebble bed dense experiment facility [J]. Nuclear Techniques, 2017, 40(4): 40605-040605.
[7]	CHEN Jie, ZHOU Tao, LIU Liang, XIA Bangyang. Study on mass flow distribution of CSR1000 [J]. Nuclear Techniques, 2017, 40(3): 30605-030605.
[8]	JING Jianping, JIA Bin, LEI Lei, BI Jinsheng, ZUO Jiaxu, LIU Yaning, ZHANG Chunming, ZHANG Dalin. Characteristic of core flow and heat transfer of different fuel ball arrangement modes in molten salt reactor [J]. Nuclear Techniques, 2017, 40(2): 20602-020602.
[9]	HU Chuanwei, E Yanzhi, ZOU Yang, XU Hongjie. Research on GPU parallelization of fluid dynamics process of molten salt reactor core [J]. Nuclear Techniques, 2017, 40(11): 110601-110601.
[10]	PAN Deng, YU Xiaohan, ZOU Yang, E Yanzhi, XU Bo, ZHOU Zhenhua, HE Jie. CFD-simulation of structured packed beds molten salt reactors on pressure drop and heat transfer [J]. Nuclear Techniques, 2016, 39(8): 80604-080604.
[11]	ZHOU Zhenhua, PAN Deng, CHEN Yushuang, HUANG Jianping, YU Xiaohan, WANG Naxiu. Core flow distribution design of molten salt reactor with liquid fuel [J]. Nuclear Techniques, 2016, 39(5): 50601-050601.
[12]	LYU Xiaowen, CHEN Changqi, XIA Xiaobin, HE Jie, ZHANG Zhihong, CAI Jun. Numerical simulation to dispersion of radioactive airborne effluents in near-field of 2-MW TMSR-LF1 [J]. Nuclear Techniques, 2016, 39(5): 50603-050603.
[13]	HE Peifeng, XU Bin, LUO Ying, YU Hao, MA Ziqi, SUN Shanwen, ZHOU Jinxiong. Numerical simulation on the convective heat transfer of compressive gas in ACP100 integrated head package [J]. Nuclear Techniques, 2016, 39(10): 100601-100601.
[14]	LIN Chao, CAI Chuangxiong, WANG Kai, HE Zhaozhong, CHEN Kun. Performance analysis of the air cooling tower for nitrate natural circulation loop [J]. Nuclear Techniques, 2014, 37(12): 120601-120601.
[15]	ZOU Peng, WANG Jianjun, GE Zengfang, WANG Yiming. Feasibility research of CRDM natural circulation cooling [J]. Nuclear Techniques, 2014, 37(03): 30604-030604.

CFD investigation and optimization on flow distribution of plate-type assembly

PDF (PC)

Like

Knowledge

Abstract

Cite this article

share this article

References

Related Articles 15

Metrics

Comments

Recommended 10