Published June 1976 | Version v1
Journal article Metadata-only

Graphite matrix fuels for pulsed reactors

Creators

  • 1. Sandia Labs., Albuquerque, NM

Description

no abstract available

Additional details

Publishing Information

Journal Title
Trans. Am. Nucl. Soc.
Journal Volume
23
Series
Trans. Am. Nucl. Soc.
Journal Page Range
132

Conference

Title
Transactions of the American Nuclear Society 1976 annual meeting.
Dates
13 Jun 1976.
Place
Toronto, Canada.

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
8290850
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference, No Abstract
Descriptors DEI
ACPR REACTOR; DISPERSION NUCLEAR FUELS; FABRICATION; FUEL PELLETS; GRAPHITE; PERFORMANCE TESTING; URANIUM CARBIDES; ZIRCONIUM CARBIDES
Descriptors DEC
ACTINIDE COMPOUNDS; CARBIDES; CARBON; CARBON COMPOUNDS; ELEMENTS; ENERGY SOURCES; ENRICHED URANIUM REACTORS; FUELS; HOMOGENEOUS REACTORS; HYDRIDE MODERATED REACTORS; MIXED SPECTRUM REACTORS; NONMETALS; NUCLEAR FUELS; PULSED REACTORS; REACTOR MATERIALS; REACTORS; RESEARCH AND TEST REACTORS; RESEARCH REACTORS; SOLID FUELS; SOLID HOMOGENEOUS REACTORS; TESTING; TRANSITION ELEMENT COMPOUNDS; URANIUM COMPOUNDS; WATER COOLED REACTORS; WATER MODERATED REACTORS; ZIRCONIUM COMPOUNDS

Optional Information

Notes
Published in summary form only.