Analysis of burnup performance for a molten chloride salt fast reactor based on thorium fuel

Yipeng PENG; Chenggang YU; Deyang CUI; Shaopeng XIA; Fan ZHU; Xiangzhou CAI; Jingen CHEN

doi:10.11889/j.0253-3219.2018.hjs.41.070602

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Analysis of burnup performance for a molten chloride salt fast reactor based on thorium fuel

NUCLEAR ENERGY SCIENCE AND ENGINEERING | 更新时间：2021-05-19

- Analysis of burnup performance for a molten chloride salt fast reactor based on thorium fuel
- NUCLEAR TECHNIQUES Vol. 41, Issue 7, Article number: 070602(2018)
- 作者机构：
  
  1.中国科学院上海应用物理研究所嘉定园区上海 201800
  2.中国科学院先进核能创新研究院上海 201800
  3.中国科学院大学北京 100049
- 作者简介：
- 基金信息：
- DOI：10.11889/j.0253-3219.2018.hjs.41.070602
  CLC： TL99
- Received：20 December 2017，
  
  Revised：20 December 2017，
  
  Published：10 July 2018
- 稿件说明：
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Yipeng PENG, Chenggang YU, Deyang CUI, et al. Analysis of burnup performance for a molten chloride salt fast reactor based on thorium fuel[J]. Nuclear techniques, 2018, 41(7): 070602
DOI：

Yipeng PENG, Chenggang YU, Deyang CUI, et al. Analysis of burnup performance for a molten chloride salt fast reactor based on thorium fuel[J]. Nuclear techniques, 2018, 41(7): 070602 DOI： 10.11889/j.0253-3219.2018.hjs.41.070602.

摘要

与氟盐堆相比，氯盐快堆具有超铀核素（Transuranics，TRU）溶解度更高、中子能谱更硬、熔点更低等方面的优势。基于熔盐嬗变堆（Molten Salt Actinide Recycler and Transmuter，MOSART）的堆芯结构，采用熔盐堆在线添料和后处理程序MSR-RS（Molten Salt Reactor Reprocessing Sequence）进行分析，针对氯盐快堆的熔盐组成、后处理方式等方面进行了优化，以利于提升其增殖及嬗变性能。首先分析了不同载体盐和启动燃料对燃耗性能的影响，提出了熔盐成分优化方案；然后引入离线批处理和在线连续处理两种后方式来提升燃耗性能。结果表明：在氯盐快堆中，高重金属溶解度的NaCl更适合作为载体盐；TRU中的次锕系核素（Minor Actinides，MA）有助于提升增殖性能；采用离线批处理能够达到较好的燃耗性能，降低对后处理系统的要求。优化后的堆芯燃耗时间延长到31 a，相应的燃耗深度提高至210 GW·d·t

-1

左右，

233

U的积累量达到8300 kg，并且最终消耗了约12000 kg的TRU，嬗变率为62.1%。

Abstract

Background

Compared with the molten fluoride salt reactor

the molten chloride salt fast reactor (MCFR) has outstanding advantages in terms of transuranics (TRU) solubility

neutron spectrum and melting point

so it is very crucial to study neutron performances of the MCFR to evaluate its feasibility.

Purpose

This study aims to optimize the composition and reprocessing method of the molten salt to enhance the breeding and burnup performance of MCFR.

Methods

Based on the molten salt reactor reprocessing sequence (MSR-RS)

the effect of different carrier salt and starting fuel on burnup performance are analyzed and the composition of molten salt is optimized. Then

off-line batch reprocessing and on-line continuous reprocessing are introduced to improve burnup performance.

Results

After a series of optimization

the burnup-time is extended to 31 a

the burnup level is increased to 210GW·d·t

-1

the production of

233

U is 8300 kg

and finally 12000 kg of TRU is consumed corresponding to transmutation rate of 62.1%.

Conclusion

NaCl is a more suitable carrier salt for MCFR

and minor actinides (MA) in the TRU also helps to improve the breeding performance. Batch reprocessing can not only achieve great burnup performance but also reduces the requirement for the reprocessing system.

关键词

Keywords

references

US Department of Energy. A technology roadmap for generation Ⅳ nuclear energy systems[R]. USA: Nuclear Energy Research Advisory Committee and the Generation Ⅳ International Forum, 2002: GIF-002-00.

江绵恒 , 徐洪杰 , 戴志敏 . 未来先进核裂变——TMSR核能系统 . 中国科学院院刊 , 2012 . 27 ( 3 ): 366 - 374 . DOI: 10.3969/j.issn.1000-3045.2012.03.016 http://doi.org/10.3969/j.issn.1000-3045.2012.03.016 http://kns.cnki.net/KCMS/detail/detail.aspx?filename=kyyx201203017&dbname=CJFD&dbcode=CJFQ .

Mianheng JIANG , Hongjie XU , Zhimin DAI . Advanced fission energy program-TMSR nuclear energy system . Bulletin of Chinese Academy of Sciences , 2012 . 27 ( 3 ): 366 - 374 . DOI: 10.3969/j.issn.1000-3045.2012.03.016 http://doi.org/10.3969/j.issn.1000-3045.2012.03.016 http://kns.cnki.net/KCMS/detail/detail.aspx?filename=kyyx201203017&dbname=CJFD&dbcode=CJFQ .

R Hargraves , R Moir . Liquid fluoride thorium reactors:an old idea in nuclear power gets reexamined . American Scientist , 2010 . 98 ( 4 ): 304 - 313 . DOI: 10.1511/2010.85.304 http://doi.org/10.1511/2010.85.304 http://cn.bing.com/academic/profile?id=8b2fb2ef65afc3d1d4bae04f8eb15c75&encoded=0&v=paper_preview&mkt=zh-cn .

E S Bettis , R W Schroeder , G A Cristy , . The aircraft reactor experiment-design and construction . Nuclear Science & Engineering , 1957 . 2 ( 6 ): 804 - 825 . DOI: 10.13182/NSE57-A35495 http://doi.org/10.13182/NSE57-A35495 https://www.researchgate.net/publication/255327052_The_aircraft_reactor_experiment-design_and_construction .

W K Ergen , A D Callihan , C B Mills , . The aircraft reactor experiment-physics . Nuclear Science & Engineering , 1957 . 2 ( 6 ): 826 - 840 . DOI: 10.13182/NSE57-A35496 http://doi.org/10.13182/NSE57-A35496 http://cn.bing.com/academic/profile?id=0d5163f7ecd00d1ee85d773401ede67b&encoded=0&v=paper_preview&mkt=zh-cn .

Bulmer J J, Gift E H, Holl R J, et al. Reactor design and feasibility study: fused salt fast breeder[R]. Tennessee: Oak Ridge School of Reactor Technology, 1956. https://www.osti.gov/biblio/4319127

Smith J, Simmons W E. An assessment of a 2500 MWe molten chloride salt fast reactor[R]. Winfrith: United Kingdom Atomic Energy Authority, 1974.

Taube M. Fast reactors using molten chloride salts as fuel[R]. Switzerland: Swiss Federal Institute of Reactor Research, 1978.

Taube M, Heer W. Reactor with very low fission product inventory[R]. Switzerland: Swiss Federal Institute of Reactor Research, 1980.

Taube M, Ligou J. Molten chlorides fast breeder reactor problems and possibilities[R]. Switzerland: Swiss Federal Institute of Reactor Research, 1972. https://www.researchgate.net/publication/255416414_MOLTEN_CHLORIDES_FAST_BREEDER_REACTOR_PROBLEMS_AND_POSSIBILITIES

M Taube , J Ligou . Molten plutonium chlorides fast breeder reactor cooled by molten uranium chloride . Annals of Nuclear Science & Engineering , 1974 . 1 ( 4 ): 277 - 281 . DOI: 10.1016/0302-2927(74)90045-2 http://doi.org/10.1016/0302-2927(74)90045-2 http://cn.bing.com/academic/profile?id=f00ff5aa797a42c52ede1802c83bb35e&encoded=0&v=paper_preview&mkt=zh-cn .

Scott I, Abram T, Negri O. Stable salt reactor design concept[C]. Proceedings of the International Thorium Energy Conference: Gateway to Thorium Energy, 2015.

A Huke , G Ruprecht , D Weißbach , . The dual fluid reactor-a novel concept for a fast nuclear reactor of high efficiency . Annals of Nuclear Energy , 2015 . 80 225 - 235 . DOI: 10.1016/j.anucene.2015.02.016 http://doi.org/10.1016/j.anucene.2015.02.016 http://cn.bing.com/academic/profile?id=5fd312918e4d1aca1d748bcdeaff7421&encoded=0&v=paper_preview&mkt=zh-cn .

Chloride reactor research founded by DOE[EB/OL]. 2015-7-31. http://energyfromthorium.com/2016/01/16/doe-terrapower/ http://energyfromthorium.com/2016/01/16/doe-terrapower/ .

Operational & long-term shutdown reactors[EB/OL]. 2018-2-18. https://www.iaea.org/PRIS/WorldStatistics/OperationalReactorsByCountry.aspx https://www.iaea.org/PRIS/WorldStatistics/OperationalReactorsByCountry.aspx .

OECD, NEA, IEA. Technology roadmap: nuclear energy[R]. 2015.

Ignatiev V, Feynberg O, GnidoiI, et al. Progress in development of Li, Be, Na/F molten salt actinide recycler & transmuter concept[C]. Proceedings of ICAPP, 2007, 7: 13-18.

闫凯. TZM合金高温抗氧化涂层的研究[D]. 南京: 南京航空航天大学, 2010. DOI: 10.7666/d.y1825359 http://dx.doi.org/10.7666/d.y1825359 . http://cdmd.cnki.com.cn/Article/CDMD-10287-1011252872.htm

YAN Kai. Study on high temperature oxidation-resistant coating on TZM alloy[D]. Nanjing: Nanjing University of Aeronautics and Astronautics, 2010. DOI: 10.7666/d.y1825359.y1825359 http://dx.doi.org/10.7666/d.y1825359.y1825359 .

Alexander L G. Molten salt fast reactors[C]. Proceedings of Conference of Breeding, Economics, and Safety in Large Fast Power Reactors, 1963: 553.

李光超 , 邹杨 , 余呈刚 , . 基于熔盐快堆的模型优化与Th-U增殖性能研究 . 核技术 , 2017 . 40 ( 2 ): 020603 DOI: 10.11889/j.0253-3219.2017.hjs.40.020603 http://doi.org/10.11889/j.0253-3219.2017.hjs.40.020603 http://www.j.sinap.ac.cn/hejishu/CN/abstract/abstract717.shtml .

Guangchao LI , Yang ZOU , Chenggang YU , . Model optimization and analysis of Th-U breeding based on MSFR . Nuclear Techniques , 2017 . 40 ( 2 ): 020603 DOI: 10.11889/j.0253-3219.2017.hjs.40.020603 http://doi.org/10.11889/j.0253-3219.2017.hjs.40.020603 http://www.j.sinap.ac.cn/hejishu/CN/abstract/abstract717.shtml .

C Y Zou , X Z Cai , D Z Jiang , . Optimization of temperature coefficient and breeding ratio for a graphite-moderated molten salt reactor . Nuclear Engineering & Design , 2015 . 281 114 - 120 . DOI: 10.1016/j.nucengdes.2014.11.022 http://doi.org/10.1016/j.nucengdes.2014.11.022 http://cn.bing.com/academic/profile?id=823605c5bac3a478f7b3870a652275d1&encoded=0&v=paper_preview&mkt=zh-cn .

C G Yu , X X Li , X Z Cai , . Minor actinide incineration and Th-U breeding in a small FLiNaK molten salt fast reactor . Annals of Nuclear Energy , 2017 . 99 335 - 344 . DOI: 10.1016/j.anucene.2016.09.025 http://doi.org/10.1016/j.anucene.2016.09.025 http://cn.bing.com/academic/profile?id=003ffa9adcf1804d47878bdd96e0d510&encoded=0&v=paper_preview&mkt=zh-cn .

C G Yu , X X Li , X Z Cai , . Analysis of minor actinides transmutation for a molten salt fast reactor . Annals of Nuclear Energy , 2015 . 85 597 - 604 . DOI: 10.1016/j.anucene.2015.06.014 http://doi.org/10.1016/j.anucene.2015.06.014 http://cn.bing.com/academic/profile?id=2b888902aabbb19c08ce40c8926312d9&encoded=0&v=paper_preview&mkt=zh-cn .

A Mourogov , P M Bokov . Potentialities of the fast spectrum molten salt reactor concept:REBUS-3700 . Energy conversion and management , 2006 . 47 ( 17 ): 2761 - 2771 . DOI: 10.1016/j.enconman.2006.02.013 http://doi.org/10.1016/j.enconman.2006.02.013 https://www.researchgate.net/publication/51987307_Potentialities_of_the_fast_spectrum_molten_salt_reactor_concept_REBUS-3700 .

Merle-Lucotte E, Heuer D, Brun C L, et al. Fast thorium molten salt reactors started with plutonium[C]. International Congress on Advances in Nuclear Power Plants, OAI, 2006.

Yokoo T, Inoue T. Mass balance of the Pu and minor actinides recycling metal fuel system[C]. 15th OECD/NEA Information Exchange Meeting on Actinide and Fission Product Partitioning and Transmutation, 1998.

S Delpech , E Merle-Lucotte , D Heuer , . Reactor physic and reprocessing scheme for innovative molten salt reactor system . Journal of Fluorine Chemistry , 2009 . 130 ( 1 ): 11 - 17 . DOI: 10.1016/j.jfluchem.2008.07.009 http://doi.org/10.1016/j.jfluchem.2008.07.009 http://cn.bing.com/academic/profile?id=071886c4c3b6bed43e606ce63b48756d&encoded=0&v=paper_preview&mkt=zh-cn .

Mitachi K, Suzuki T, Nakanishi Y, et al. A preliminary design study of a small molten salt reactor for effective use of thorium resource[C]. Proceedings 7th International Conference on Nuclear Engineering, Tokyo, Japan, 1999: 7144.

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