Published 1974 | Version v1
Journal article Metadata-only

Fission-gas-release assessment of the E7 coolant voiding dynamics

Creators

  • 1. Univ. of New Mexico, Albuquerque

Description

no abstract available

Additional details

Additional titles

Augmented title (English)
LMFBR

Publishing Information

Journal Title
Trans. Amer. Nucl. Soc.
Journal Volume
19
Series
Trans. Amer. Nucl. Soc.
Journal Page Range
262-263

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
6173012
Subject category
S61: RADIATION PROTECTION AND DOSIMETRY; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference, No Abstract
Descriptors DEI
FAILURES; FISSION PRODUCTS; FUEL PINS; HYDRAULICS; LIQUID FLOW; LMFBR TYPE REACTORS; PERFORMANCE TESTING; REACTOR SAFETY; TREAT REACTOR
Descriptors DEC
AIR COOLED REACTORS; BREEDER REACTORS; ENRICHED URANIUM REACTORS; EPITHERMAL REACTORS; EXPERIMENTAL REACTORS; FAST REACTORS; FBR TYPE REACTORS; FLUID FLOW; FUEL ELEMENTS; GAS COOLED REACTORS; GRAPHITE MODERATED REACTORS; HOMOGENEOUS REACTORS; ISOTOPES; LIQUID METAL COOLED REACTORS; RADIOACTIVE MATERIALS; REACTOR COMPONENTS; REACTORS; RESEARCH AND TEST REACTORS; SAFETY; SOLID HOMOGENEOUS REACTORS; TEST REACTORS; TESTING; THERMAL REACTORS

Optional Information

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