Published November 1975 | Version v1
Journal article Metadata-only

Loss-of-flow test F1 on an FFTF-type fuel element

Creators

  • 1. Argonne National Lab., IL

Description

no abstract available

Additional details

Publishing Information

Journal Title
Trans. Am. Nucl. Soc.
Journal Volume
22
Series
Trans. Am. Nucl. Soc.
Journal Page Range
427-428

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
7251775
Subject category
S61: RADIATION PROTECTION AND DOSIMETRY; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference, No Abstract
Descriptors DEI
FUEL ELEMENTS; LMFBR TYPE REACTORS; LOSS OF FLOW; MELTING; REACTOR OPERATION; SIMULATION; TREAT REACTOR
Descriptors DEC
ACCIDENTS; AIR COOLED REACTORS; BREEDER REACTORS; ENRICHED URANIUM REACTORS; EPITHERMAL REACTORS; EXPERIMENTAL REACTORS; FAST REACTORS; FBR TYPE REACTORS; GAS COOLED REACTORS; GRAPHITE MODERATED REACTORS; HOMOGENEOUS REACTORS; LIQUID METAL COOLED REACTORS; OPERATION; PHASE TRANSFORMATIONS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTORS; RESEARCH AND TEST REACTORS; SOLID HOMOGENEOUS REACTORS; TEST REACTORS; THERMAL REACTORS

Optional Information

Notes
Published in Summary Form Only.