Published 1974 | Version v1
Journal article Metadata-only

Analysis of fuel-element failure in the L5 TREAT transient test simulating a loss-of-coolant-flow accident in an FTR-type reactor

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
261

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
6173092
Subject category
S61: RADIATION PROTECTION AND DOSIMETRY; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference, No Abstract
Descriptors DEI
FAILURES; FFTF REACTOR; FUEL PINS; LOSS OF FLOW; PERFORMANCE TESTING; REACTOR SAFETY; TRANSIENTS; TREAT REACTOR
Descriptors DEC
ACCIDENTS; AIR COOLED REACTORS; ENRICHED URANIUM REACTORS; EPITHERMAL REACTORS; EXPERIMENTAL REACTORS; FAST REACTORS; FUEL ELEMENTS; GAS COOLED REACTORS; GRAPHITE MODERATED REACTORS; HOMOGENEOUS REACTORS; LIQUID METAL COOLED REACTORS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTORS; RESEARCH AND TEST REACTORS; RESEARCH REACTORS; SAFETY; SODIUM COOLED REACTORS; SOLID HOMOGENEOUS REACTORS; TEST REACTORS; TESTING; THERMAL REACTORS

Optional Information

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