PLUGM: a coupled thermal-hydraulic computer model for freezing melt flow in a channel. [LMFBR]

Conference · Fri Jan 01 00:00:00 EST 1982

OSTI ID:6756656

Pilch, M

PLUGM is a coupled thermal-hydraulic computer model for freezing liquid flow and plugging in a cold channel. PLUGM is being developed at Sandia National Laboratories for applications in Sandia's ex-vessel Core Retention Concept Assessment Program and in Sandia's LMFBR Transition Phase Program. The purpose of this paper is to introduce PLUGM and demonstrate how it can be used in the analysis of two of the core retention concepts under investigation at Sandia: refractory brick crucibles and particle beds.

• Research Organization: Sandia National Labs., Albuquerque, NM (USA)
• DOE Contract Number: AC04-76DP00789
• OSTI ID: 6756656
• Report Number(s): SAND-82-2183C; CONF-821037-12; ON: DE83001172
• Resource Relation: Conference: 10. water reactor safety research information conference, Gaithersburg, MD, USA, 12 Oct 1982; Other Information: Portions of document are illegible
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
COMPUTER CODES
P CODES
CORE CATCHERS
HEAT TRANSFER
TEMPERATURE DISTRIBUTION
LMFBR TYPE REACTORS
MELTDOWN
HYDRAULICS
CORIUM
HYDRODYNAMICS
MAGNESIUM OXIDES
REACTOR CORE DISRUPTION
REACTOR SAFETY
ACCIDENTS
ALKALINE EARTH METAL COMPOUNDS
BREEDER REACTORS
CHALCOGENIDES
ENERGY TRANSFER
EPITHERMAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
FLUID MECHANICS
LIQUID METAL COOLED REACTORS
MAGNESIUM COMPOUNDS
MECHANICS
OXIDES
OXYGEN COMPOUNDS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTORS
SAFETY
220900* - Nuclear Reactor Technology- Reactor Safety
210500 - Power Reactors
Breeding