Published 1993 | Version v1
Journal article

Safety evaluation of core components exposed to air during an LBLOCA

  • 1. Los Alamos National Lab., NM (United States)

Description

An analysis was performed to determine the peak heat structure temperature of internal reactor components during the gamma-heating phase of a large-break loss-of-coolant accident (LBLOCA) in a heavy-water reactor. During this phase, the reactor is scrammed, the coolant in the moderator tank is replaced by air, and fuel and control rod tubes are cooled internally by forced convection via the emergency core-cooling system (ECCS) water. However, the safety rods, reflector assemblies, and tank wall continue to heat up as a result of gamma deposition and relatively low heat transfer rates; heat transfer in the safety rods, reflector assemblies, and the tank wall occurs primarily from natural/mixed convection and radiation heat transfer. The ECCS discharges at the top of the moderator tank in the form of droplets and film. Thus, the gamma-heating phase of the LBLOCA is characterized by natural/mixed air convection heat transfer, conduction heat transfer, droplet flow, thermal radiation heat transfer, and air-droplet interfacial heat transfer

Additional details

Publishing Information

Journal Title
Transactions of the American Nuclear Society
Journal Volume
68
Journal Page Range
p. 272-273.
ISSN
0003-018X
CODEN
TANSAO

Conference

Title
American Nuclear Society (ANS) annual meeting.
Dates
20-24 Jun 1993.
Place
San Diego, CA (United States).

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
25022760
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
CORE FLOODING SYSTEMS; DESIGN BASIS ACCIDENTS; ECCS; HEAVY WATER COOLED REACTORS; LOSS OF COOLANT; REACTOR CORES; REACTOR SAFETY; SAFETY ANALYSIS
Descriptors DEC
ACCIDENTS; ENGINEERED SAFETY SYSTEMS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTOR PROTECTION SYSTEMS; REACTORS; SAFETY

Optional Information

Secondary number(s)
CONF-930601--.