Thermal-hydraulic analysis for the upgraded MIT Nuclear Research Reactor

被引：0

作者：

Hu, LW ^{[1
]}

Bernard, JA ^{[1
]}

机构：

[1] MIT, Cambridge, MA 02139 USA

来源：

1997 IEEE NUCLEAR SCIENCE SYMPOSIUM - CONFERENCE RECORD, VOLS 1 & 2 | 1998年

关键词：

D O I：

暂无

中图分类号：

TH7 [仪器、仪表];

学科分类号：

0804 ; 080401 ; 081102 ;

摘要：

The thermal-hydraulic analysis performed for a planned upgrade of the MIT Research Reactor from 5 to 6-7 MW using the existing heat removal equipment is reported. This upgrade is one of several options under consideration for the relicensing of the MIT Research Reactor in 1999. Included in this paper is a description of the calculations of thermal-hydraulic limits which include limiting safety system settings (LSSS) and safety limits (SL). The LSSS and SL were respectively chosen to avoid onset of nucleate boiling and flow instability during steady-state operation. These analyses were performed using the MULti-CHannel-II or MULCH-II code which was developed and benchmarked at ha for design and safety analysis of the MIT Research Reactor.

引用

页码：908 / 912

页数：5

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