Analysis of reactor material experiments investigating corium crust stability and heat transfer in jet impingement flow

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

OSTI ID:5239661

Sienicki, J J; Spencer, B W

Presented is an analysis of the results of the CSTI-1, CSTI-3, and CWTI-11 reactor material experiments in which a jet of molten corium initially at 3080/sup 0/K was directed downward upon a stainless steel plate. The experiments are a continuation of a program of reactor material tests investigating LWR severe accident phenomena. Objective of the present analysis is to determine the existence or nonexistence of a corium crust during impingement from comparison of the measured heatup of the plate (as measured by thermocouples imbedded immediately beneath the steel surface) with model calculations assuming alternately the presence and absence of a stable crust during impingement.

• Research Organization: Argonne National Lab., IL (USA)
• DOE Contract Number: W-31-109-ENG-38
• OSTI ID: 5239661
• Report Number(s): CONF-850810-9; ON: DE85007980; TRN: 85-022119
• Resource Relation: Conference: National heat transfer conference, Denver, CO, USA, 4 Aug 1985; 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
MELTDOWN
WATER COOLED REACTORS
CORIUM
HEAT TRANSFER
REACTOR SAFETY EXPERIMENTS
SIMULATION
ACCIDENTS
ENERGY TRANSFER
REACTOR ACCIDENTS
REACTORS
220900* - Nuclear Reactor Technology- Reactor Safety