Source term calculations for accident management strategies for VVER-1000 reactors: part 1: text
Creators
- 1. Abteilung Forschungsreaktor, Bereich Verfahrens-und Umwelttechnik, Oesterreichisches Forschungszentrum Seibersdorf GmbH (Austria)
- 2. Abteilung Informationstechnik, Bereich Industrielle Messtechnik und Informationsverarbeitung, Oesterreichisches Forschungszentrum Seibersdorf GmbH (Austria)
Description
This report describes the effect of different accident management strategies on the source term for a TMLB'-type sequence in a Pressurized Water Reactor of the type VVER-1000 up to the time when no more fission products are released from the core-concrete-interaction because the temperature of the debris is so low that it solidifies. Using the Source Term Code Package (STCP) the following scenarios were calculated: (1) Reference case without spray and LP ECC systems. (2) All spray and LP ECC systems including the coolers are available after 7 hours. (3) All spray and LP ECC systems including the coolers are available after 10 hours. (4) One spray and one LP ECC system but no coolers are available after 10 hours. (5) All spray and LP ECC systems but no coolers are available after 10 hours; the pressure increase is limited by filtered containment venting. The results show that in any case water should be supplied to the containment as soon as possible. Furthermore the effectiveness of the other accident management strategies are rated. The proposed measures reduce the source term by a factor of 2 up to several orders of magnitude. (author)
Availability note (English)
Available from Austrian Research Centre Seibersdorf, 2444 Seibersdorf (AT).Additional details
Publishing Information
- Imprint Pagination
- 50 p.
- Report number
- OEFZS-A--3730
INIS
- Country of Publication
- Austria
- Country of Input or Organization
- Austria
- INIS RN
- 27062094
- Subject category
- S61: RADIATION PROTECTION AND DOSIMETRY; S99: GENERAL AND MISCELLANEOUS;
- Resource subtype / Literary indicator
- Non-conventional Literature
- Descriptors DEI
- COMPUTERIZED SIMULATION; CONTAINMENT; CORE SPRAY SYSTEMS; ECCS; ENVIRONMENTAL IMPACTS; MELTDOWN; REACTOR ACCIDENTS; S CODES; SOURCE TERMS; WWER-5 REACTOR
- Descriptors DEC
- ACCIDENTS; COMPUTER CODES; ENGINEERED SAFETY SYSTEMS; ENRICHED URANIUM REACTORS; POWER REACTORS; PWR TYPE REACTORS; REACTOR PROTECTION SYSTEMS; REACTORS; SIMULATION; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS; WWER TYPE REACTORS