Published January 1977 | Version v1
Report

Modeling of pool growth

Creators

  • 1. Argonne National Lab., IL

Description

In studies of postaccident fuel behavior in LMFBRs, it is of interest to examine the interaction of the core debris with the reactor cavity environment in the event that the fuel melts through the reactor and guard vessels. The core debris may thereupon come in contact with the structural concrete or the materials of an engineered core retention system, if one is provided. Such materials presently being considered include commercial refractories of high alumina, magnesia, or zirconia content. A relatively simple model of the growth of core debris pools in refractory materials was developed earlier, and was used in the computer program GROWS. Briefly, the model consisted of striking a heat balance over the fuel pool to determine the distribution of the decay heat rejection in the upward, downward, and horizontal directions. Heat rejected in the downward and horizontal directions was then assumed to result in pool growth by melting of the concrete or core retainer material. Improvements to the model are discussed

Additional details

Publishing Information

Imprint Title
Proceedings of second Post-Accident Heat Removal ''information exchange''
Journal Page Range
p. 279-284.
Report number
SAND--76-9008

Conference

Title
Meeting on post-accident heat removal information exchange.
Dates
13 Nov 1975.
Place
Albuquerque, New Mexico, USA.

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
8334999
Subject category
S61: RADIATION PROTECTION AND DOSIMETRY; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
AFTER-HEAT REMOVAL; G CODES; HEAT TRANSFER; LMFBR TYPE REACTORS; MATHEMATICAL MODELS; MELTDOWN; REACTOR ACCIDENTS
Descriptors DEC
ACCIDENTS; BREEDER REACTORS; COMPUTER CODES; ENERGY TRANSFER; EPITHERMAL REACTORS; FAST REACTORS; FBR TYPE REACTORS; LIQUID METAL COOLED REACTORS; REACTORS