Calculation of Source Terms for Water-cooled Fusion Reactor Based on Deviation Effect Nuclide Screening Method

Guo Qingyang; Zhang Jingyu; Zhang Huijie; Wang Qingbin

doi:10.13832/j.jnpe.2022.05.0001

Volume 43 Issue 5

Oct. 2022

Turn off MathJax

Article Contents

Article Navigation > Nuclear Power Engineering > 2022 > 43(5): 1-6

Guo Qingyang, Zhang Jingyu, Zhang Huijie, Wang Qingbin. Calculation of Source Terms for Water-cooled Fusion Reactor Based on Deviation Effect Nuclide Screening Method[J]. Nuclear Power Engineering, 2022, 43(5): 1-6. doi: 10.13832/j.jnpe.2022.05.0001

Citation:

Guo Qingyang, Zhang Jingyu, Zhang Huijie, Wang Qingbin. Calculation of Source Terms for Water-cooled Fusion Reactor Based on Deviation Effect Nuclide Screening Method[J]. Nuclear Power Engineering, 2022, 43(5): 1-6. doi: 10.13832/j.jnpe.2022.05.0001

Citation:

PDF( 2384 KB)

Calculation of Source Terms for Water-cooled Fusion Reactor Based on Deviation Effect Nuclide Screening Method

doi: 10.13832/j.jnpe.2022.05.0001

1.
Institute of High Energy Physics, Chinese Academy of Sciences, Beijing, 100049, China
2.
School of Nuclear Science and Engineering, North China Electric Power University, Beijing, 102206, China

Received Date: 2021-11-09
Rev Recd Date: 2022-01-25

Available Online: 2022-10-12

Publish Date: 2022-10-12

Abstract

Abstract

The activated corrosion products are the main radioactive source terms in the normal operation of water-cooled fusion reactor, and are generally solved by analytical methods, but analytical methods cannot improve the calculation speed while meeting the accuracy requirements. In this paper, a nuclide screening method based on quantitative deviation effect analysis is proposed, which defines the two parameters of radioactivity and dose rate as deviation effect indicators. By analyzing the deviation effect indicators, nuclides meeting the acceptance criteria are screened to determine the target nuclides required for calculation. This analysis method can not only meet the accuracy requirements, but also improve the calculation efficiency. This nuclide screening method is applied to the source term analysis of activated corrosion products in the International Thermonuclear Experimental reactor (ITER) limiter-outer cladding water-cooled loop (LIM-OBB), and compared with the high-precision benchmark solution under this issue. The results show that the relative deviations of the specific activity calculation results of important activated corrosion product nuclides such as ⁵⁷Co, ⁵⁸Co, ⁵⁵Fe, and ⁵¹Cr compared with the benchmark solution are all controlled within 1.5%; The calculation efficiency of the nuclide screening method is 279 times higher than that of the benchmark solution.
- Activated corrosion products,
- Water-cooled fusion reactor,
- Deviation effect,
- Calculation efficiency,
- Source term analysis

FullText(HTML)

References(16)

References

[1]	刘原中. 轻水堆一迥路中放射性核素浓度的计算方法及计算机程序[J]. 辐射防护,1986, 6(6): 409-424.
[2]	RAFIQUE M, MIRZA N M, MIRZA S M, et al. Review of computer codes for modeling corrosion product transport and activity build-up in light water reactors[J]. Nukleonika, 2010, 55(3): 263-269.
[3]	KANG S, SEJVAR J. CORA-II model of PWR corrosion-product transport[R]. Pittsburgh: Westinghouse Electric Corp, 1985: 11-169.
[4]	NISHIMURA T, KASAHARA K. Improvement of crud behavior evaluation code (ACE)[C]//Proceedings of 1998 JAIF International Conference on Water Chemistry in Nuclear Power Plants. Kashiwakazi: Japan Atomic Industrial Forum, 1998.
[5]	BESLU P, FREJAVILLE G, LALEX A. A computer code PACTOLE to predict activation and transport of corrosion products in a PWR[C]//Proceedings of an International Conference Organized by the British Nuclear Energy Society. Bournemouth: ICE, 1978.
[6]	DI PACE L, DACQUAIT F, SCHINDLER P, et al. Development of the PACTITER code and its application to safety analyses of ITER primary cooling water system[J]. Fusion Engineering and Design, 2007, 82(3): 237-247. doi: 10.1016/j.fusengdes.2006.11.002
[7]	LI L, ZHANG J Y, SONG W, et al. CATE: a code for activated corrosion products evaluation of water-cooled fusion reactor[J]. Fusion Engineering and Design, 2015, 100: 340-344. doi: 10.1016/j.fusengdes.2015.06.193
[8]	LI L, ZHANG J Y, HE S X, et al. The development of two-phase three-node model used to simulate the transport of ACPs[J]. Progress in Nuclear Energy, 2017, 97: 99-105. doi: 10.1016/j.pnucene.2016.12.015
[9]	ZHANG J Y, LI L, HE S X, et al. Development of a three-zone transport model for activated corrosion products analysis of Tokamak cooling water system[J]. Fusion Engineering and Design, 2016, 109-111: 407-410. doi: 10.1016/j.fusengdes.2016.02.091
[10]	张竞宇,李璐,宋文,等. 水冷聚变堆活化腐蚀产物源项分析程序开发[J]. 原子能科学技术,2015, 49(S1): 68-74.
[11]	FORREST R A, KOPECKY J, SUBLET J C. The European activation file: EAF-2007 neutron-induced cross section library[R]. Abingdon: EURATOM/UKAEA Fusion Association, 2007: 19-21.
[12]	郭庆洋,张竞宇,陈义学. 聚变堆水冷回路中多物相活化腐蚀产物计算分析[J]. 核技术,2019, 42(6): 060602. doi: 10.11889/j.0253-3219.2019.hjs.42.060602
[13]	GUO Q Y, ZHANG J Y, FANG S, et al. Activation analysis of coolant in a water-cooled loop of China fusion engineering test reactor[J]. Fusion Engineering and Design, 2018, 136: 694-698. doi: 10.1016/j.fusengdes.2018.03.059
[14]	HINDMARSH A C. Ordinary differential equation system solver[R]. Livermore: Lawrence Livermore National Laboratory, 1992.
[15]	RADHAKRISHNAN K, HINDMARSH AC. Description and use of LSODE, the Livermore solver for ordinary differential equations[R]. Washington: NASA, 1993.
[16]	KARDITSAS P J. Activation product transport using TRACT: ORE estimation of an ITER cooling loop[J]. Fusion Engineering and Design, 1999, 45(2): 169-185. doi: 10.1016/S0920-3796(99)00004-6