Published October 1995
| Version v1
Miscellaneous
Loss of coolant accidents (LOCAs) in VVER-440 reactors: state-of-the-art analysis techniques
Creators
- 1. Winfrith Technology Centre, AEA Technology, Dorchester (United Kingdom)
Description
An assessment is presented of a Large Break LOCA for a WWER-440/V213 type reactor, using the best estimate thermal-hydraulics code TRAC-PF1/MOD1 to investigate the importance of 3-dimensional flow effects within the reactor vessel of a WWER. The TRAC model is described and Large Break LOCA results are discussed. It was found that a 3-D representation of the vessel is required in order to capture the main thermal-hydraulic behavior during a LBLOCA. (J.B.) 2 figs
Additional details
Publishing Information
- Imprint Title
- Proceedings of the international topical meeting on VVER safety
- Imprint Pagination
- 416 p.
- Journal Page Range
- p. 206-209.
- Report number
- INIS-mf--14715
Conference
- Title
- International topical meeting on VVER safety.
- Dates
- 21-23 Sep 1995.
- Place
- Prague (Czech Republic).
INIS
- Country of Publication
- Czech Republic
- Country of Input or Organization
- Czech Republic
- INIS RN
- 27022843
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- COMPUTERIZED SIMULATION; LOSS OF COOLANT; REACTOR SAFETY; SAFETY ANALYSIS; T CODES; THREE-DIMENSIONAL CALCULATIONS; WWER TYPE REACTORS
- Descriptors DEC
- ACCIDENTS; COMPUTER CODES; ENRICHED URANIUM REACTORS; POWER REACTORS; PWR TYPE REACTORS; REACTOR ACCIDENTS; REACTORS; SAFETY; SIMULATION; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS