PASCAR: Long burning small modular reactor based on natural circulation

被引:57
作者
Choi, Sungyeol [1 ]
Cho, Jae-Hyun [1 ]
Bae, Moo-Hoon [1 ]
Lim, Jun [1 ]
Puspitarini, Dina [1 ]
Jeun, Ji Hoon [1 ]
Joo, Han-Gyu [1 ]
Hwang, Il Soon [1 ]
机构
[1] Seoul Natl Univ, Dept Nucl Engn, Seoul 151742, South Korea
关键词
LEAD; DESIGN; STEELS; CORROSION; BEHAVIOR; COOLANT;
D O I
10.1016/j.nucengdes.2011.03.005
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
PASCAR is a 100 MWt/35 MWe lead-bismuth-cooled small modular reactor which requires no on-site refueling and well suits to be used as a distributed power source in either a single unit or a cluster for electricity, heat supply, and desalination. This paper includes both steady-state and transient performance evaluations for neutronics and thermal-hydraulics. Through design optimization studies for minimizing a burn-up reactivity loss, the metallic fuels-loaded core was designed with less than 1$ reactivity swing over 20-year cycle. A radial peaking power location shows the slow inward migration from outer enrichment zones while maintaining peaking factor within 1.35, reducing radiation damage and corrosion duty of high temperature environments. Equipped with coolant flow path large enough to ensure low pressure drop, this reactor is intended to operate by only natural circulation of chemically inert coolant within relatively low temperature range, 320-420 degrees C. Peak outlet temperature is nearly 450 degrees C where an Al-containing duplex cladding has sufficient corrosion resistance. Despite of 50% decrease of fuel thermal conductivity after swelling, inherent negative reactivity feedback and passive decay heat removal capability could secure an ample safety margin of peak fuel centerline temperature in tow safety analyses, unprotected transient overpower and unprotected loss of heat sink. The likelihood of loss of coolant, loss of flow, and local blockage is virtually eliminated by employing respectively a double-walled vessel, pump-less cooling, and cross-flow allowed open square assemblies. Simple fabrication, modular construction, and long burning cycle would compensate for economic disadvantages over smaller power and lower temperature than those of conventional fast reactors. (C) 2011 Elsevier B.V. All rights reserved.
引用
收藏
页码:1486 / 1499
页数:14
相关论文
共 54 条
[1]   MYRRHA: A multipurpose accelerator driven system for research & development [J].
Abderrahim, HA ;
Kupschus, P ;
Malambu, E ;
Benoit, P ;
Van Tichelen, K ;
Arien, B ;
Vermeersch, F ;
D'hondt, P ;
Jongen, Y ;
Ternier, S ;
Vandeplassche, D .
NUCLEAR INSTRUMENTS & METHODS IN PHYSICS RESEARCH SECTION A-ACCELERATORS SPECTROMETERS DETECTORS AND ASSOCIATED EQUIPMENT, 2001, 463 (03) :487-494
[2]  
Alcouffe R., 1995, DANTSYS: A Diffusion Accelerated Neutral Particle Transport Code System
[3]  
[Anonymous], 2009, NUCL TECHNOLOGY REV
[4]  
[Anonymous], 2007, IAEATECDOC1569
[5]  
Bae M.H., 2009, T KOR NUCL SOC SPRIN
[6]   An overview of corrosion issues for the design and operation of high-temperature lead- and lead-bismuth-cooled reactor systems [J].
Ballinger, RG ;
Lim, J .
NUCLEAR TECHNOLOGY, 2004, 147 (03) :418-435
[7]   Corrosion behavior of steels in flowing lead-bismuth [J].
Barbier, F ;
Rusanov, A .
JOURNAL OF NUCLEAR MATERIALS, 2001, 296 :231-236
[8]  
Brown N.W., 2006, UCRLMI220282 LAWR LI
[9]   Economic features of integral, modular, small-to-medium size reactors [J].
Carelli, M. D. ;
Garrone, P. ;
Locatelli, G. ;
Mancini, M. ;
Mycoff, C. ;
Trucco, P. ;
Ricotti, M. E. .
PROGRESS IN NUCLEAR ENERGY, 2010, 52 (04) :403-414
[10]  
Chang Y.I., 2005, ANLSMFR1