Safety of Super LWR, (I) - Safety system design

被引:37
作者
Ishiwatari, Y
Oka, Y
Koshizuka, S
Yamaji, A
Liu, J
机构
[1] Univ Tokyo, Sch Engn, Nucl Profess Sch, Tokai, Ibaraki 3191188, Japan
[2] Univ Tokyo, Sch Engn, Dept Quantum Engn & Syst Sci, Bunkyo Ku, Tokyo 1138656, Japan
[3] Univ Tokyo, Sch Engn, Dept Nucl Engn & Management, Bunkyo Ku, Tokyo 1138656, Japan
关键词
once-through cooling cycle; supercritical-pressure; downward-flow water rod; safety principle; safety system design;
D O I
10.3327/jnst.42.927
中图分类号
TL [原子能技术]; O571 [原子核物理学];
学科分类号
0827 [核科学与技术]; 082701 [核能科学与工程];
摘要
This paper describes design concept of safety system of the high-temperature supercritical pressure light water cooled reactor with downward-flow water rods (Super LWR). Since this reactor is once-through cooling system without water level and coolant circulation, the fundamental safety requirement is keeping core coolant flow rate while that of light water reactors (LWR) is keeping coolant inventory. "Coolant supply from cold-leg" and "coolant outlet at hotleg" are needed for it. The advantage of the once-through cooling system is that reactor depressurization induces core coolant flow and cools the core. The downward-flow water rod system enhances this effect because the top dome and the water rods supply its water inventory to the core like an "in-vessel accumulator." The safety system of the Super LWR is designed referring to those of LWR in consideration of its characteristics and safety principle. "Coolant supply" is kept by high-pressure auxiliary feedwater system and low-pressure core injection system. "Coolant outlet" is kept by safety relief valves and automatic depressurization system. The Super LWR is equipped with two independent shutdown systems: reactor scram system and standby liquid control system. The capacities and the actuation conditions determined in this study are to be used in safety analysis.
引用
收藏
页码:927 / 934
页数:8
相关论文
共 11 条
[1]
ISHIKWATARI Y, 2003, P INT C GLB ENV ADV
[2]
Safety of Super LWR, (II) - Safety analysis at supercritical pressure [J].
Ishiwatari, Y ;
Oka, Y ;
Koshizuka, S ;
Yamaji, A ;
Liu, J .
JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY, 2005, 42 (11) :935-948
[3]
ISHIWATARI Y, 2003, P INT C GLOB ENV ADV
[4]
ISHIWATARI Y, 2002, P INT C ADV NUCL POW
[5]
Ishiwatari Y., 2003, P GLOBAL 2003 NEW OR, P2335
[6]
ISHIWATARI Y, 2004, P 2004 INT C ADV NUC
[7]
Refinement of transient criteria and safety analysis for a high-temperature reactor cooled by supercritical water [J].
Kitoh, K ;
Koshizuka, S ;
Oka, Y .
NUCLEAR TECHNOLOGY, 2001, 135 (03) :252-264
[8]
KITOH K, 1988, NUCL TECHNOL, V123, P223
[9]
Core design of a high-temperature fast reactor cooled by supercritical light water [J].
Mukohara, T ;
Koshizuka, SI ;
Oka, Y .
ANNALS OF NUCLEAR ENERGY, 1999, 26 (16) :1423-1436
[10]
OKA Y, 2003, P GLOBAL 2003 NEW OR, P1128