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 |
[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
|
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