Published 1983 | Version v1
Book Metadata-only

Thermal hydraulic analysis of main-steam-line-break accidents as potential initiators for reactor vessel pressurized thermal shock

Creators

  • 1. Energy Div., Los Alamos National Lab., Los Alamos, NM 87544

Description

Results are presented from two thermal hydraulic analysis of postulated main-steam-line breaks for the Oconee nuclear power plant. One calculation assumes runaway feedwater supply, whereas normal feedwater management is used in the other. The analyses were performed with the TRAC-PD2 code. The objective was to provide primary coolant temperature and pressure histories to assist in evaluating possible reactor-vessel pressurized thermal-shock concerns

Additional details

Publishing Information

Publisher
American Nuclear Society.
Imprint Place
LaGrange Park, IL (USA)
ISBN
0-89448-110-X
Imprint Title
Thermal hydraulics of nuclear reactors
Journal Page Range
p. 997-1005.

Conference

Title
2. international topical meeting on nuclear reactor thermal hydraulics (ANS).
Dates
11-13 Jan 1983.
Place
Santa Barbara, CA (USA).

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
17089563
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
FEEDWATER; HYDRAULICS; LOSS OF COOLANT; OCONEE-1 REACTOR; OCONEE-2 REACTOR; OCONEE-3 REACTOR; PRESSURE DEPENDENCE; PRESSURIZATION; PRIMARY COOLANT CIRCUITS; REACTOR VESSELS; RUPTURES; STEAM LINES; T CODES; TEMPERATURE DEPENDENCE; THERMAL SHOCK; THERMODYNAMICS
Descriptors DEC
ACCIDENTS; COMPUTER CODES; CONTAINERS; COOLING SYSTEMS; ENRICHED URANIUM REACTORS; FAILURES; HYDROGEN COMPOUNDS; OXYGEN COMPOUNDS; PIPELINES; POLAR SOLVENTS; POWER REACTORS; PWR TYPE REACTORS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTORS; SOLVENTS; THERMAL REACTORS; WATER; WATER COOLED REACTORS; WATER MODERATED REACTORS