Published October 1980 | Version v1
Journal article Metadata-only

Parametric study of radioactive release from a breached containment

Creators

  • 1. Isr At Energy Comm, Tel Aviv

Description

A hypothetical accident is analyzed, in which an external (out-of-plant) natural or man-made event causes a loss-of-coolant accident after penetrating the containment wall. The computer codes CONTEMPT and RELAP4 have been used to study the containment thermal-hydraulic behavior during the accident. Results are given in the form of graphs showing the thermal-hydraulic response of the containment and the profile of radioactive release to the atmosphere. The physical model and input data are discussed. 13 refs

Additional details

Additional titles

Augmented title (English)
CONTEMPT code, RELAP4 code

Publishing Information

Journal Title
Nucl. Technol.
Journal Volume
50
Journal Issue
3
Series
Nucl. Technol.
Journal Page Range
219-224
ISSN
0029-5450

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
14761482
Subject category
S61: RADIATION PROTECTION AND DOSIMETRY; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Descriptors DEI
C CODES; CONTAINMENT SYSTEMS; HEAT TRANSFER; HYDRAULICS; LOSS OF COOLANT; NUCLEAR POWER PLANTS; PWR TYPE REACTORS; R CODES; RADIOACTIVE EFFLUENTS; REACTOR ACCIDENTS; STEAM
Descriptors DEC
ACCIDENTS; COMPUTER CODES; CONTAINMENT; ENERGY TRANSFER; MATERIALS; NUCLEAR FACILITIES; POWER PLANTS; RADIOACTIVE MATERIALS; RADIOACTIVE WASTES; REACTORS; THERMAL POWER PLANTS; WASTES; WATER COOLED REACTORS; WATER MODERATED REACTORS