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Title: Emergency Decay Heat Removal in a GEN-IV Gas-Cooled Fast Reactor

A series of transient analyses using the system code RELAP5-3d has been performed to confirm the efficacy of a proposed hybrid active/passive combination approach to the decay heat removal for an advanced 2400 MWt GEN-IV gas-cooled fast reactor. The accident sequence of interest is a station blackout simultaneous with a small break (10 sq.inch/0.645 m{sup 2}) in the reactor vessel. The analyses cover the three phases of decay heat removal in a depressurization accident: (1) forced flow cooling by the power conversion unit (PCU) coast down, (2) active forced flow cooling by a battery powered blower, and (3) passive cooling by natural circulation. The blower is part of an emergency cooling system (ECS) that by design is to sustain passive decay heat removal via natural circulation cooling 24 hours after shutdown. The RELAP5 model includes the helium-cooled reactor, the ECS (primary and secondary side), the PCU with all the rotating machinery (turbine and compressors) and the heat transfer components (recuperator, pre-cooler and inter-cooler), and the guard containment that surrounds the reactor and the PCU. The transient analysis has demonstrated the effectiveness of passive decay heat removal by natural circulation cooling when the guard containment pressure is maintained at or abovemore » 800 kPa. (authors)« less
Authors:
; ;  [1]
  1. Brookhaven National Laboratory, P.O. Box 5000, Upton, NY 11973-5000 (United States)
Publication Date:
OSTI Identifier:
20995571
Resource Type:
Conference
Resource Relation:
Conference: 14. international conference on nuclear engineering (ICONE 14), Miami, FL (United States), 17-20 Jul 2006; Other Information: Country of input: France
Publisher:
American Society of Mechanical Engineers - ASME, New York (United States)
Research Org:
The ASME Foundation, Inc., Three Park Avenue, New York, NY 10016-5990 (United States)
Country of Publication:
United States
Language:
English
Subject:
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; ACCIDENTS; AFTER-HEAT REMOVAL; BLOWERS; COMPRESSORS; CONTAINMENT; CONVERSION; COOLING; COOLING SYSTEMS; DEPRESSURIZATION; DESIGN; FAST REACTORS; HEAT EXCHANGERS; HELIUM COOLED REACTORS; NATURAL CONVECTION; OUTAGES; REACTOR VESSELS; SHUTDOWN; TRANSIENTS; TURBINES