氯盐冷却快堆子通道程序开发及初步验证

doi:10.11889/j.0253-3219.2019.hjs.42.010604

Nuclear Science and Techniques ›› 2019, Vol. 42 ›› Issue (1): 10604-010604.doi: 10.11889/j.0253-3219.2019.hjs.42.010604

Previous Articles Next Articles

Development and preliminary validation of a sub-channel analysis code for molten chloride-cooled fast reactor

Ming LIN^1,²,Maosong CHENG¹(),Zhimin DAI¹

1. Shanghai Institute of Applied Physics, Chinese Academy of Sciences, Shanghai 201800, China
2. University of Chinese Academy of Sciences, Beijing 100049, China

Received:2018-10-23 Revised:2018-11-26 Online:2019-01-10 Published:2019-01-25
Contact: Maosong CHENG E-mail:mscheng@sinap.ac.cn
Supported by:
Supported by Strategic Pilot Science and Technology Project of Chinese Academy of Sciences (No.XD02001005)

Abstract

Abstract: Background

Molten salt-cooled reactor (MSR) is one of six Generation IV advanced reactor concepts, molten chloride-cooled fast reactor (MCCFR) is one of MSRs which uses high temperature chloride-salt as coolant and has great advantages of high temperature, low pressure and harden neutron energy spectrum, as well as potential in inherent safety.

Purpose

This study aims to develop and valid a sub-channel analysis code for calculation and analysis of the thermal-hydraulic characteristics of MCCFR.

Methods

The single-phase sub-channel analysis approach is applied to coolant thermal-hydraulic analysis to solve transient mass, momentum and energy conservation equations. And based on the 7-bundle geometry, the pressure drop model and the turbulent mixing model applied in the sub-channel analysis code for molten chloride-cooled reactor are specifically analyzed and validated by comparison with these numerical results from Fluent.

Results

The results indicate that the numerical results of the developed sub-channel analysis code with Rogers-Rosehart turbulent mixing model and Cheng-Todreas pressure drop model are in good agreement with that from Fluent in the case of steady state and transient.

Conclusion

The development and preliminary validation of the sub-channel analysis code will provide an effective design and analysis tool for the new chloride salt cooled fast reactor.

Key words: Molten chloride-salt reactor, Sub-channel analysis, Pressure drop model, Turbulent mixing model, Fluent

CLC Number:

TL333

Ming LIN, Maosong CHENG, Zhimin DAI. Development and preliminary validation of a sub-channel analysis code for molten chloride-cooled fast reactor[J].Nuclear Science and Techniques, 2019, 42(1): 10604-010604.

Figures/Tables 11

Fig.1

Table 1

Fig.2

Fig.3

Fig.4

Table 2

Fig.5

Table 3

Fig.6

Fig.7

Fig.8

References 17

1	OECD NEA. Technology roadmap update for generation IV nuclear energy systems[R].GENIV International Forum.OECD Nuclear Energy Agency for the Generation IV International Forum, January 2014.
2	江绵恒,徐洪杰,戴志敏 .未来先进核裂变能——TMSR核能系统[J].中国科学院院刊,2012,27(3):366−374.
	JIANG Mianheng , XU Hongjie , DAI Zhimin .Advanced nuclear fission energy-TMSR nuclear energy systems[J].Bulletin of Chinese Academy of Sciences,2012,27(3):366−374.
3	张洁,李明海,何龙,等 .1 GW固态燃料熔盐堆运行瞬态分析[J].核技术,2016,39(10):100605.DOI:10.11889/j.0253-3219.2016.hjs.39.100605. doi: 10.11889/j.0253-3219.2016.hjs.39.100605.
	ZHANG Jie , LI Minghai , HE Long ,et al .Transient analysis with 1-GW solid fuel molten salt reactor[J].Nuclear Techniques,2016,39(10):100605.DOI:10.11889/j.0253-3219.2016.hjs.39.100605. doi: 10.11889/j.0253-3219.2016.hjs.39.100605.
4	Zhang D , Qiu S , Liu C ,et al .Steady thermal hydraulic analysis for a molten salt reactor[J].Nuclear Science and Techniques,2008,19(3):187−192.
5	Bulmer J J .Fused salt fast breeder: reactor design and feasibility study[M].United States Atomic Energy Commission, Technical Information Service Extension,1957.
6	Liu X J , Scarpelli N .Development of a sub-channel code for liquid metal cooled fuel assembly[J].Annals of Nuclear Energy,2015,77:425−435.
7	Kim W S , Kim Y G , Kim Y J .A subchannel analysis code MATRA-LMR for wire wrapped LMR subassembly[J].Annals of Nuclear Energy,2002,29(3):303−321.
8	Dobson G P , O’Neill J M .SABRE, user guide for version 4[M].AEA Technology,1992.
9	陈选相,吴攀,单建强 .钠冷快堆分析程序ATHAS-LMR的子通道模型[J].原子能科学技术,2012,46(6):695−700.
	CHEN Xuanxiang , WU Pan , SHAN Jianqiang .Subchannel model of analysis code ATHAS-LMR for LMFBR[J].Atomic Energy Science and Technology,2012,46(6):695−700.
10	Chen H L , Zhou G M , Li S Z ,et al .Subchannel analysis of fuel assemblies of a lead–alloy cooled fast reactor[J].Progress in Nuclear Energy,2015,78:182−189.DOI:10.1016/j.pnucene.2014.09.009. doi: 10.1016/j.pnucene.2014.09.009.
11	Zhou G M , Chen Z , Zhao P C ,et al .Validation of a subchannel analysis code for heavy liquid metal cooled reactors using CFD code[C].International Seminar on Subchannel Analysis, CFD Modeling and Verification, CHF Experiment and Benchmarking, Xi'an, China,2013.DOI:10.13140/RG.2.1.5187.7522. doi: 10.13140/RG.2.1.5187.7522.
12	Shwageraus E , Hejzlar P , Driscoll M J .Liquid salt cooled flexible conversion ratio fast reactor: neutronic design[J].Nuclear Engineering and Design,2009,239(12):2626−2645.
13	Li Y Y , Xu X K , Wang X X ,et al .Survey and evaluation of equations for thermophysical properties of binary/ternary eutectic salts from NaCl, KCl, MgCl₂, CaCl₂, ZnCl₂for heat transfer and thermal storage fluids in CSP[J].Solar Energy,2017,152:57−79.DOI:10.1016/j.solener.2017.03.019. doi: 10.1016/j.solener.2017.03.019.
14	Gnielinski V .New equations for heat and mass transfer in turbulent pipe and channel flow[J].International Chemmcal Engineering,1976,16(2):359−368.
15	Petroski R C .Design of a 2 400 MW liquid-salt cooled flexible conversion ratio reactor[D].Massachusetts:Massachusetts Institute of Technology,2010.
16	Jeong H Y , Ha K S , Kwon Y M ,et al .A dominant geometrical parameter affecting the turbulent mixing rate in rod bundles[J].International Journal of Heat and Mass Transfer,2007,50(5−6):908−918.
17	杨世铭,陶文铨 .传热学[M].第四版. 北京:高等教育出版社,2006:398−399.
	YANG Shiming , TAO Wenquan .Heat transfer[M].4th Ed. Beijing:Higher Education Press,2006:398−399.

模型Model	Re/ 10⁴	S_m/D	Correlation forβ
Seale	4.6~9.1	0.100	0.029 68Re ^?0.1
	4.6~19.0	0.375	0.016 83Re ^?0.1
Rowe-Angle	4.2~12.6	0.036	0.063Re ^?0.1
Rowe-Angle	6.0~18	0.149	0.021Re ^?0.1
Rogers-Rosehart	—	—	0.005(D_h /S_m )Re ^?0.1
Rogers-Tahir	0.81~4.95	—	0.005(D_h /S_m )?(S_m /D)^?0.105 Re ^?0.1
Gabraith-Knudsen	—	0.028	0.001 57Re ^0.23
		0.063	0.002 87Re ^0.12
		0.127	0.002 28Re ^0.12
		0.228	0.006 0Re ^0.01

热传输模型 Heat transfer model	压降模型 Pressure drop model	湍流交混模型(S_m /D) Turbulent mixing models
Gnielinski	Blausius	Rowe and angle (0.149)
	McAdams	Seale (0.100)
	Cheng-Todreas	Rogers-Rosehart
		Rogers-Tahir
		Gabraith-Knudsen (0.228)

湍流交混模型Turbulent mixing model	压降模型Pressure drop model
湍流交混模型Turbulent mixing model	McAdams	Blausius	Cheng-Todreas
Rowe-Angle	7.787 8	8.195 3	2.451 2
Seale	7.790 6	8.195 3	2.454 0
Rogers-Rosehart	7.790 6	8.198 1	2.465 2
Rogers-Tahir	7.790 6	8.198 1	2.468 0
Gabraith-Knudsen	7.787 8	8.195 3	2.451 2

Development and preliminary validation of a sub-channel analysis code for molten chloride-cooled fast reactor

RichHTML

PDF (PC)

Like

Knowledge

Abstract

Cite this article

share this article

Figures/Tables 11

References 17

Related Articles 1

Metrics

Comments

Recommended 10