Published October 1983 | Version v1
Journal article

Thermohydraulics in a high-temperature gas-cooled reactor primary loop during early phases of unrestricted core heatup accidents

  • 1. Brookhaven National Laboratory Upton, NY 11973

Description

no abstract available

Additional details

Publishing Information

Journal Title
Trans. Am. Nucl. Soc.
Journal Volume
45
Series
Trans. Am. Nucl. Soc.
Journal Page Range
841-843
ISSN
0003-018X

Conference

Title
American Nuclear Society winter meeting.
Dates
30 Oct - 4 Nov 1983.
Place
San Francisco, CA (USA).

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
15053570
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference, No Abstract
Descriptors DEI
COMPUTER CALCULATIONS; FLUID-STRUCTURE INTERACTIONS; HTGR TYPE REACTORS; HYDRAULICS; PRIMARY COOLANT CIRCUITS; R CODES; REACTOR ACCIDENTS; REACTOR CORES; THERMODYNAMICS
Descriptors DEC
ACCIDENTS; COMPUTER CODES; COOLING SYSTEMS; GAS COOLED REACTORS; GRAPHITE MODERATED REACTORS; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTORS

Optional Information

Notes
Published in summary form only.
Secondary number(s)
CONF-831047--.