Published June 1974 | Version v1
Journal article Metadata-only

Evaluation of the fuel coolant interaction source for FEFP loop design

Creators

  • 1. Argonne National Lab., IL

Description

no abstract available

Additional details

Additional titles

Augmented title (English)
LMFBR

Publishing Information

Journal Title
Trans. Amer. Nucl. Soc.
Journal Volume
18
Series
Trans. Amer. Nucl. Soc.
Journal Page Range
262

Conference

Title
Annual meeting of the American Nuclear Society.
Dates
23 Jun 1974.
Place
Philadelphia, PA.

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
5152572
Subject category
S61: RADIATION PROTECTION AND DOSIMETRY;
Resource subtype / Literary indicator
Conference, No Abstract
Descriptors DEI
ETR REACTOR; FAILURES; FFTF REACTOR; FUEL PINS; FUEL-COOLANT INTERACTIONS; IN PILE LOOPS; LMFBR TYPE REACTORS; TESTING
Descriptors DEC
BREEDER REACTORS; ENRICHED URANIUM REACTORS; EPITHERMAL REACTORS; FAST REACTORS; FBR TYPE REACTORS; FUEL ELEMENTS; IRRADIATION REACTORS; ISOTOPE PRODUCTION REACTORS; LIQUID METAL COOLED REACTORS; REACTOR COMPONENTS; REACTOR EXPERIMENTAL FACILITIE; REACTORS; RESEARCH AND TEST REACTORS; RESEARCH REACTORS; SODIUM COOLED REACTORS; TANK TYPE REACTORS; TEST REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS

Optional Information

Notes
Published in summary form only.