The PANDA tests for the SWR 1000 passive containment cooling system
- 1. Paul Scherrer Institut (PSI), CH-5232 Villigen PSI (Switzerland)
Description
Since 1992, Siemens has been developing the SWR 1000, a new boiling water reactor with passive safety features. This development has been performed in close co-operation with the German nuclear utilities and with support from various European partners. Within the European Union sponsored project 'BWR R and D Cluster for Innovative Passive Safety Systems' and a bilateral contract between Siemens and the Paul Scherrer Institute, the passive containment cooling system of the SWR 1000 design has been investigated in the large-scale PANDA test facility at the Paul Scherrer Institute. A series of six tests were performed to simulate transients selected to cover a range of failure assumptions and accident severity, including core heat up and hydrogen generation. The results graphically demonstrate the self regulating character of the passive heat removal systems and their effectiveness, even under severe load, in limiting the containment pressurisation. Some tentative conclusions for the SWR1000 are drawn, to be established by detailed analyses of the data, to support models and codes for application to plant transients. (author)
Additional details
Publishing Information
- Publisher
- Japan Society of Mechanical Engineers
- Imprint Place
- Tokyo (Japan)
- Imprint Title
- ICONE-7: Proceedings of the 7th international conference on nuclear engineering
- Imprint Pagination
- 4252 p.
- Journal Page Range
- [14 p.]
Conference
- Title
- 7. international conference on nuclear engineering
- Acronym
- ICONE-7
- Dates
- 19-23 Apr 1999
- Place
- Tokyo (Japan)
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 31010881
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- AFTER-HEAT REMOVAL; BWR TYPE REACTORS; CONTAINMENT; COOLING SYSTEMS; HYDRAULICS; PERFORMANCE TESTING; PRESSURIZATION; REACTOR ACCIDENTS; SIMULATION; TEST FACILITIES; THERMODYNAMICS
- Descriptors DEC
- ACCIDENTS; ENERGY SYSTEMS; ENRICHED URANIUM REACTORS; POWER REACTORS; REACTORS; REMOVAL; TESTING; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- This CD-ROM can be used for WINDOWS 95/98/NT, MACINTOSH and UNIX; Acrobat Reader 3.0.1 is included; Data in PDF format, Track No. 06, ICONE-7316