Published October 1995 | Version v1
Miscellaneous Metadata-only

Cernavoda CANDU severe accident evaluation

Creators

  • 1. Institute for Nuclear Research, PO Box 70, Str. Colibasi 78, R-0300 Pitesti, (Romania)

Description

The paper presents a Probabilistic Risk Assessment on the CANDU unit which is now in commissioning phase in Romania. The aim of the study is to determine the degree of this reactor safety and to analyse a hypothetical severe accident. This implies reactor failure processes, core melt progression and environmental release of fission products. The study is applied to the Cernavoda CANDU unit and the results are compared with other similar CANDU 600 accidents. The accident taken into consideration its loss of all heat sinks. The paper presents also comparison with other reactor types with respect to this hypothetical accident. (Author) 2 Figs., 1 Tab., 3 Refs

Availability note (English)

Available from Romanian Nuclear Energy Association AREN, University Politehnica of Bucharest.
Part of:
International Symposium on Nuclear Energy - Nuclear Safety. Proceedings of the Romanian Nuclear Energy Association International Symposium on Nuclear Energy (SIEN'95)

Additional details

Publishing Information

Publisher
Romanian Nuclear Energy Association 'AREN' in cooperation with University 'Politehnica' of Bucharest.
Imprint Place
Bucharest (Romania)
Imprint Title
SIEN'95 - International Symposium on Nuclear Energy. Nuclear Safety
Imprint Pagination
392 p.
Journal Page Range
p. 60-63.

Conference

Title
SIEN '95 - International symposium on nuclear energy.
Dates
20-21 Oct 1995.
Place
Bucharest (Romania).

INIS

Country of Publication
Romania
Country of Input or Organization
Romania
INIS RN
27015639
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference, Non-conventional Literature
Descriptors DEI
CERNAVODA-1 REACTOR; EVALUATION; F CODES; HEAT SINKS; LOSS OF COOLANT; M CODES; MAXIMUM CREDIBLE ACCIDENT; REACTOR ACCIDENTS
Descriptors DEC
ACCIDENTS; CANDU TYPE REACTORS; COMPUTER CODES; DESIGN BASIS ACCIDENTS; HEAVY WATER COOLED REACTORS; HEAVY WATER MODERATED REACTORS; NATURAL URANIUM REACTORS; PHWR TYPE REACTORS; POWER REACTORS; PRESSURE TUBE REACTORS; REACTORS; THERMAL REACTORS

Optional Information

Notes
Proceedings published in a single volume. Imprint:Proceedings published in a single volume.