Very high temperature behavior of HTGR core materials

Conference · Sun Jan 01 00:00:00 EST 1978

OSTI ID:6386212

Soo, P; Uneberg, G; Sabatini, R; Shroy, R E; Sastre, C; Schweitzer, D G

A description is given of experiments to investigate the behavior of HTGR core materials during hypothetical heatup accidents in which the core temperature is assumed to reach values between 2400/sup 0/C and the graphite sublimation range (>3600/sup 0/C). The work includes BISO coated fuel particle failure, simulated fission product migration in core graphite, and graphite sublimation behavior.

• Research Organization: Brookhaven National Lab., Upton, NY (USA)
• DOE Contract Number: EY-76-C-02-0016
• OSTI ID: 6386212
• Report Number(s): BNL-NUREG-25323; CONF-781144-9; TRN: 79-005114
• Resource Relation: Conference: 2. US-Japan seminar on HTGR safety technology, Fuji, Japan, 24 Nov 1978
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
HTGR TYPE REACTORS
REACTOR ACCIDENTS
REACTOR MATERIALS
THERMAL STRESSES
COATED FUEL PARTICLES
FUEL ELEMENT FAILURE
GRAPHITE
REACTOR CORES
REACTOR SAFETY
SUBLIMATION
ACCIDENTS
CARBON
ELEMENTS
EVAPORATION
FUEL PARTICLES
GAS COOLED REACTORS
GRAPHITE MODERATED REACTORS
NONMETALS
PHASE TRANSFORMATIONS
REACTOR COMPONENTS
REACTORS
SAFETY
STRESSES
220900* - Nuclear Reactor Technology- Reactor Safety
210300 - Power Reactors
Nonbreeding
Graphite Moderated