Scoping systems analysis of a 350 MWt modular liquid metal cooled reactor

Conference · Tue Jan 01 00:00:00 EST 1985

OSTI ID:5341915

Morris, E E; Rhow, S K; Switick, D M

The systems analysis code SASSYS was used to explore the sensitivity of the system response to various inherent reactivity feedback mechanisms and design features for a small, liquid-metal-cooled reactor during the first 1000 s following the initiation of an unprotected loss-of-flow and/or loss-of-primary-heat-removal transient. The results show that to maximize the inherent safety of small, liquid-metal-cooled reactors, inherent feedback mechanisms should be accounted for in establishing design features such as the flow coastdown time constant and the control rod suspension system. The results also indicate insensitivity of the system response to the operation or non-operation of heat removal systems during the early part of an unprotected loss-of-flow transient.

• Research Organization: Argonne National Lab., IL (USA); General Electric Co., Sunnyvale, CA (USA)
• DOE Contract Number: W-31-109-ENG-38
• OSTI ID: 5341915
• Report Number(s): CONF-850410-45; ON: DE85012117
• Resource Relation: Conference: ANS/ENS fast reactor safety meeting, Knoxville, TN, USA, 21 Apr 1985
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
LIQUID METAL COOLED REACTORS
LOSS OF FLOW
COMPUTER CODES
FEEDBACK
REACTIVITY
S CODES
SYSTEMS ANALYSIS
ACCIDENTS
REACTOR ACCIDENTS
REACTORS
220900* - Nuclear Reactor Technology- Reactor Safety
210500 - Power Reactors
Breeding