Modeling of DECL accident in the reactor containment by the CONTAIN 2.0 code
Creators
- 1. Islamic Azad Univ., Teheran (Iran, Islamic Republic of). Dept. of Nuclear Engineering, Science and Research Branch
Description
In this paper, a specific type of the Loss of Coolant Accident (LOCA), the DECL (Double Ended Cold Leg) break, that means totally Guillotine type of break in the cold leg pipe, has been modeled. The accident is simulated with the CONTAIN 2.0 code. In the event of a LOCA accident, coolant mass and energy are released to the containment through the break. This causes an increase of pressure and temperature in the containment. The modeling is performed in the VVER-1000 reactor containment. The analysis includes average pressure in the containment and temperature distribution in sample cells in the long-time. The results are compared with the existing reports on studies that used the ANGAR code. Results show that the CONTAIN 2.0 code is an adaptable tool for the analysis of nuclear events such as DECL accident. (orig.)
Additional details
Publishing Information
- Journal Title
- Kerntechnik (1987)
- Journal Volume
- 78
- Journal Issue
- 5
- Journal Page Range
- p. 443-446
- ISSN
- 0932-3902
- CODEN
- KERNEU
INIS
- Country of Publication
- Germany
- Country of Input or Organization
- Germany
- INIS RN
- 45021830
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Descriptors DEI
- C CODES; COMPUTERIZED SIMULATION; CONTAINMENT; FRACTURES; LOSS OF COOLANT; PIPES; SIMULATION; TEMPERATURE DISTRIBUTION; TEMPERATURE RANGE 0065-0273 K; TEMPERATURE RANGE 0273-0400 K; TIME DEPENDENCE; WWER TYPE REACTORS
- Descriptors DEC
- ACCIDENTS; COMPUTER CODES; ENRICHED URANIUM REACTORS; FAILURES; POWER REACTORS; PWR TYPE REACTORS; REACTOR ACCIDENTS; REACTORS; SIMULATION; TEMPERATURE RANGE; THERMAL REACTORS; TUBES; WATER COOLED REACTORS; WATER MODERATED REACTORS