New PANDA Tests to Investigate Effects of Light Gases on Passive Safety Systems
Creators
- 1. Laboratory for Thermal-Hydraulics, Paul Scherrer Institut, 5232 Villigen PSI (Switzerland)
Description
The large- scale thermal-hydraulic PANDA facility (located at PSI in Switzerland), has been used over the last few years for investigating different passive decay- heat removal systems and containment phenomena for the next generation of light water reactors (Simplified Boiling Water Reactor: SBWR; European Simplified Boiling Water Reactor: ESBWR; Siedewasserreaktor: SWR-1000). Currently, as part of the European Commission 5. EURATOM Framework Programme project 'Testing and Enhanced Modelling of Passive Evolutionary Systems Technology for Containment Cooling' (TEMPEST), a new series of tests is being planned in the PANDA facility to experimentally investigate the distribution of non-condensable gases inside the containment and their effect on the performance of the 'Passive Containment Cooling System' (PCCS). Hydrogen release caused by the metal-water reaction in the case of a postulated severe accident will be simulated in PANDA by injecting helium into the reactor pressure vessel. In order to provide suitable data for Computational Fluid Dynamic (CFD) code assessment and improvement, the instrumentation in PANDA has been upgraded for the new tests. In the present paper, a detailed discussion is given of the new PANDA tests to be performed to investigate the effects of light gas on passive safety systems. The tests are scheduled for the first half of the year 2002. (authors)
Additional details
Publishing Information
- Publisher
- American Nuclear Society - ANS
- Imprint Place
- La Grange Park (United States)
- ISBN
- 0-89448-663-2
- Imprint Pagination
- 8 p.
Conference
- Title
- 2002 International congress on advances in nuclear power plants
- Acronym
- ICAPP'02
- Dates
- 9-13 Jun 2002
- Place
- Hollywood, FL (United States)
INIS
- Country of Publication
- United States
- Country of Input or Organization
- France
- INIS RN
- 40044623
- Subject category
- S42: ENGINEERING; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- AFTER-HEAT REMOVAL; BWR TYPE REACTORS; CONTAINMENT; COOLING; COOLING SYSTEMS; EURATOM; HELIUM; MOLTEN METAL-WATER REACTIONS; PRESSURE VESSELS; REACTOR ACCIDENTS; SAFETY; SIMULATION; SWITZERLAND; THERMAL HYDRAULICS
- Descriptors DEC
- ACCIDENTS; CONTAINERS; DEVELOPED COUNTRIES; ELEMENTS; ENERGY SYSTEMS; ENRICHED URANIUM REACTORS; EUROPE; EUROPEAN UNION; FLUID MECHANICS; FLUIDS; GASES; HYDRAULICS; INTERNATIONAL ORGANIZATIONS; MECHANICS; NONMETALS; POWER REACTORS; RARE GASES; REACTORS; REMOVAL; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS; WESTERN EUROPE
Optional Information
- Notes
- 12 refs.