Published 1974 | Version v1
Journal article Metadata-only

UNCLE: a computer code to predict the performance of advanced fuels in breeder reactors

Creators

  • 1. Argonne National Lab., IL

Description

no abstract available

Additional details

Publishing Information

Journal Title
Trans. Amer. Nucl. Soc.
Journal Volume
19
Series
Trans. Amer. Nucl. Soc.
Journal Page Range
96-97

Conference

Title
Meeting of the American Nuclear Society.
Dates
27 Oct 1974.
Place
Washington, District of Columbia, USA.

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
6173475
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference, No Abstract
Descriptors DEI
COMPUTER CODES; FUEL ELEMENTS; LMFBR TYPE REACTORS; MECHANICAL PROPERTIES; NUCLEAR FUELS; PERFORMANCE; PHYSICAL RADIATION EFFECTS; SPECIFICATIONS; U CODES
Descriptors DEC
BREEDER REACTORS; ENERGY SOURCES; EPITHERMAL REACTORS; FAST REACTORS; FBR TYPE REACTORS; FUELS; LIQUID METAL COOLED REACTORS; RADIATION EFFECTS; REACTOR COMPONENTS; REACTOR MATERIALS; REACTORS

Optional Information

Notes
See CONF-741017-- Published in summary form only.