SSC analysis of the GEMs for reactivity control in PRISM
The performance of three Gas Expansion Modules (GEMS) utilized the Advanced Liquid Metal Reactor (ALMR) concept, PRISM, was analyzed using the computer code, SSC. GE has submitted the PRISM design for a Preapplication Safety Evaluation Report (PSER). The draft PSER indicated a potential weakness in the Unscrammed Loss of Flow (ULOF) event, and GE modified the design by adding three GEMs. The PRISM design was analyzed by SSC for two cases. First, the design's original response to a ULOF where one Electro Magnetic (EM) pump fails to produce a coastdown was analyzed. Then the revised design with the GEMs included was analyzed. The original design had little or no safety margin for this case. The peak fuel temperature in the hot channel was predicted to be 1358K, which is above the solidus temperature of the fuel. However, after the GEMs were added, the loss of one EM pump coastdown became a benign event. The GEM feedback was predicted by SSC to dominate the other reactivity feedbacks and the GEMS, essentially, responded like passive control rods. The fuel temperature quickly dropped below operating temperatures, while the margin to sodium boiling was predicted to be greater than 350K.
- Research Organization:
- Brookhaven National Lab., Upton, NY (United States)
- Sponsoring Organization:
- USNRC; Nuclear Regulatory Commission, Washington, DC (United States)
- DOE Contract Number:
- AC02-76CH00016
- OSTI ID:
- 6682240
- Report Number(s):
- BNL-NUREG-47978; CONF-921007-17; ON: DE93007280
- Resource Relation:
- Conference: 20. water reactor safety information meeting, Bethesda, MD (United States), 21-23 Oct 1992
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
LMFBR TYPE REACTORS
LOSS OF FLOW
REACTOR CONTROL SYSTEMS
COMPUTER CALCULATIONS
ELECTROMAGNETIC PUMPS
FAILURES
FEEDBACK
FUEL ELEMENTS
REACTIVITY
S CODES
ACCIDENTS
BREEDER REACTORS
COMPUTER CODES
CONTROL SYSTEMS
EPITHERMAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
LIQUID METAL COOLED REACTORS
PUMPS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTORS
220900* - Nuclear Reactor Technology- Reactor Safety
220400 - Nuclear Reactor Technology- Control Systems
220600 - Nuclear Reactor Technology- Research
Test & Experimental Reactors