Safety aspects of LMR (liquid metal-cooled reactor) core design

Conference · Wed Jan 01 00:00:00 EST 1986

OSTI ID:6839282

Cahalan, J E

Features contributing to increased safety margins in liquid metal-cooled reactor (LMR) design are identified. The technical basis is presented for the performance of a pool-type reactor system with an advanced metallic alloy fuel in unprotected accidents. Results are presented from analyses of anticipated transients without scram, including loss-of-flow (LOF), transient overpower (TOP), and loss-of-heat-sink (LOHS) accidents.

• Research Organization: Argonne National Lab., IL (USA)
• DOE Contract Number: W-31109-ENG-38
• OSTI ID: 6839282
• Report Number(s): CONF-860906-19; ON: DE87004979
• Resource Relation: Conference: Advances in reactor physics and safety meeting, Saratoga Springs, NY, USA, 17 Sep 1986; Other Information: Portions of this document are illegible in microfiche products
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
LMFBR TYPE REACTORS
REACTOR CORES
SAFETY
DESIGN
HEAT TRANSFER
HYDRAULICS
LOSS OF FLOW
PERFORMANCE
TRANSIENT OVERPOWER ACCIDENTS
ACCIDENTS
BREEDER REACTORS
ENERGY TRANSFER
EPITHERMAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
FLUID MECHANICS
LIQUID METAL COOLED REACTORS
MECHANICS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTORS
220900* - Nuclear Reactor Technology- Reactor Safety
210500 - Power Reactors
Breeding