Published 1976 | Version v1
Report Restricted

Modeling the response of fast reactor fuel to accident transients

Creators

Description

Progress in modeling the response of fast reactor fuel to accident transients is reported in four areas: fission gas release from grains and intragranular fuel swelling, fission gas redistribution and internal pressurization in solid fuel, fuel cracking models, and fuel plasticity modeling. Applications of models in the first two areas to assessment of the comparative dispersal potential of fuel in a CRBR hypothetical unprotected loss-of-flow accident with that in recent experiments are presented. It is concluded that the reactor case presents a greater dispersal potential

Availability note (English)

MF available from INIS under the Report Number.

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Additional details

Publishing Information

Imprint Pagination
11 p.
Report number
CONF-761001--44

Conference

Title
International meeting on fast reactor safety and related physics.
Dates
Oct 1976.
Place
Chicago, Illinois, USA.

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
8315482
Subject category
S61: RADIATION PROTECTION AND DOSIMETRY; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
EXCURSIONS; FISSION PRODUCT RELEASE; FUEL ELEMENT FAILURE; FUEL ELEMENTS; LMFBR TYPE REACTORS; LOSS OF FLOW; MATHEMATICAL MODELS; MELTDOWN; MELTING; TRANSIENTS
Descriptors DEC
ACCIDENTS; BREEDER REACTORS; EPITHERMAL REACTORS; FAST REACTORS; FBR TYPE REACTORS; LIQUID METAL COOLED REACTORS; PHASE TRANSFORMATIONS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTORS

Optional Information

Notes
Available from NTIS. $3.50.