Validation of the axial expansion reactivity worth for a metal-fueled Sodium-cooled Fast Reactor via a physical experiment

被引:3
作者
Yun, Sunghwan [1 ]
Mikhailov, Gennadii [2 ]
Kim, Sang Ji [1 ]
Lim, Jae-Yong [1 ]
机构
[1] KAERI, 989-111 Daedeok Daero, Daejeon 305353, South Korea
[2] Inst Phys & Power Engn, Bondarenko Sq 1, Obninsk 249033, Kaluga Region, Russia
基金
新加坡国家研究基金会;
关键词
BFS-109-2A; Axial expansion reactivity; Direct decomposition method; Physical experiment; Critical experiment;
D O I
10.1016/j.anucene.2017.06.034
中图分类号
TL [原子能技术]; O571 [原子核物理学];
学科分类号
0827 ; 082701 ;
摘要
For a metal-fueled SFR (Sodium-cooled Fast Reactor), the negative feedback of the reactivity due to the thermal expansion of fuel has been a principal safety mechanism to guarantee passive reactor shutdown after undercooling accidents. In this paper, an experimental model of the fuel axial expansion reactivity in a metal-fueled SFR was proposed and measured values using the BFS-109-2A critical assembly was compared with calculated values using as-built MCNP models based on the ENDF/B-VILO library. The energy-dependent axial expansion reactivity components of the BFS-109-2A model showed good agreement with those of the target core. The difference in the calculation/experiment ratio between the as built MCNP models and measurements vary from -10.2% to 2.6% for the axial expansion reactivity, meanwhile the suggested axial expansion model showed a 25% discrepancy comparing to the target core. (C) 2017 Elsevier Ltd. All rights reserved.
引用
收藏
页码:244 / 257
页数:14
相关论文
共 9 条
[1]  
[Anonymous], BFS 73 1 ASSEMBLY EX
[2]  
[Anonymous], 2003, MCNP GEN MONTE CARLO, V1.
[3]   ENDF/B-VII.0: Next generation evaluated nuclear data library for nuclear science and technology [J].
Chadwick, M. B. ;
Oblozinsky, P. ;
Herman, M. ;
Greene, N. M. ;
McKnight, R. D. ;
Smith, D. L. ;
Young, P. G. ;
MacFarlane, R. E. ;
Hale, G. M. ;
Frankle, S. C. ;
Kahler, A. C. ;
Kawano, T. ;
Little, R. C. ;
Madland, D. G. ;
Moller, P. ;
Mosteller, R. D. ;
Page, P. R. ;
Talou, P. ;
Trellue, H. ;
White, M. C. ;
Wilson, W. B. ;
Arcilla, R. ;
Dunford, C. L. ;
Mughabghab, S. F. ;
Pritychenko, B. ;
Rochman, D. ;
Sonzogni, A. A. ;
Lubitz, C. R. ;
Trumbull, T. H. ;
Weinman, J. P. ;
Brown, D. A. ;
Cullen, D. E. ;
Heinrichs, D. P. ;
McNabb, D. P. ;
Derrien, H. ;
Dunn, M. E. ;
Larson, N. M. ;
Leal, L. C. ;
Carlson, A. D. ;
Block, R. C. ;
Briggs, J. B. ;
Cheng, E. T. ;
Huria, H. C. ;
Zerkle, M. L. ;
Kozier, K. S. ;
Courcelle, A. ;
Pronyaev, V. ;
van der Marck, S. C. .
NUCLEAR DATA SHEETS, 2006, 107 (12) :2931-3059
[4]   Annular fast reactor cores with low sodium void worth for TRU burning [J].
Hong, Ser Gi ;
Kim, Sang Ji ;
Kim, Yeong Il .
NUCLEAR TECHNOLOGY, 2008, 162 (01) :1-25
[5]   Design Concept of Advanced Sodium-Cooled Fast Reactor and Related R&D in Korea [J].
Kim, Yeong-il ;
Lee, Yong Bum ;
Lee, Chan Bock ;
Chang, Jinwook ;
Choi, Chiwoong .
SCIENCE AND TECHNOLOGY OF NUCLEAR INSTALLATIONS, 2013, 2013
[6]  
Klinov D.A., 2013, DRAFT FINAL REPORT M
[7]   RESULTS AND IMPLICATIONS OF THE EXPERIMENTAL BREEDER REACTOR-II INHERENT SAFETY DEMONSTRATION TESTS [J].
PLANCHON, HP ;
GOLDEN, GH ;
SACKETT, JI ;
MOHR, D ;
CHANG, LK ;
FELDMAN, EE ;
BETTEN, PR .
NUCLEAR SCIENCE AND ENGINEERING, 1988, 100 (04) :549-557
[8]  
Ronen Yigal, 1986, CRC HDB NUCL REACTOR, VIII
[9]  
Yun S., ANN NUCL ENERG UNPUB