Published November 1975 | Version v1
Journal article Metadata-only

SST: a computer code to predict fuel response and fission product release from light-water reactor fuels during steady-state and transient conditions

Creators

  • 1. Argonne National Lab., IL

Description

no abstract available

Additional details

Additional titles

Augmented title (English)
BWR; PWR

Publishing Information

Journal Title
Trans. Am. Nucl. Soc.
Journal Volume
22
Series
Trans. Am. Nucl. Soc.
Journal Page Range
462-463

Conference

Title
American Nuclear Society 1975 winter meeting.
Dates
16 Nov 1975.
Place
San Francisco, CA, USA.

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
7251783
Subject category
S61: RADIATION PROTECTION AND DOSIMETRY; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference, No Abstract
Descriptors DEI
BWR TYPE REACTORS; COMPUTER CALCULATIONS; FISSION PRODUCT RELEASE; FUEL ELEMENTS; PERFORMANCE; PWR TYPE REACTORS; REACTOR ACCIDENTS; TRANSIENTS
Descriptors DEC
ACCIDENTS; REACTOR COMPONENTS; REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS

Optional Information

Notes
Published in Summary Form Only.