Published October 1997
| Version v1
Miscellaneous
PSA level 2 analysis for Cernavoda NPP
Creators
- 1. Nuclear Research Institute, PO Box 78, Str. Colibasi, R-0300 Pitesti (Romania)
Description
For CANDU type plant Severe Accident is defined as loss of core structural integrity and severe core melts occurrence. To analyse the accident progression means to track the progression of the accident from the onset of core melt until one is assured that no additional release of radionuclides from the containment will occur. Analysis of the physical progression of an accident using deterministic models is performed to support the following activities: level 1 success criteria evaluation, event timing determination, sensitivity studies to support containment event trees (CET) development and quantification, input preparation to source term analysis. (authors)
Availability note (English)
Available from the author(s) or Energy Info-Documentation Centre, Roma-nian Electricity Authority, RENEL - Engineering Studies and Research Group, Bldv. Energeticienilor No.8, Sector 3, R-79619 Bucharest (RO).Additional details
Publishing Information
- Publisher
- Energy Info-Documentation Centre.
- Imprint Place
- Bucharest (Romania)
- Imprint Title
- SIEN'97 - International Symposium on Nuclear Energy. Radioactive Waste Management
- Imprint Pagination
- 346 p.
- Journal Page Range
- (pt.1) p. 250-254.
Conference
- Title
- Radioactive Waste Management.
- Acronym
- SIEN'97 - International Symposium on Nuclear Energy
- Dates
- 24-25 Oct 1997.
- Place
- Bucharest (Romania).
INIS
- Country of Publication
- Romania
- Country of Input or Organization
- Romania
- INIS RN
- 29018333
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- AIR CONDITIONING; CANDU TYPE REACTORS; CERNAVODA-1 REACTOR; CONTAINMENT SYSTEMS; ECCS; ENGINEERED SAFETY SYSTEMS; FAILURE MODE ANALYSIS; NUCLEAR DAMAGE; PRIMARY COOLANT CIRCUITS; PROBABILISTIC ESTIMATION; REACTOR ACCIDENTS; REACTOR SHUTDOWN; SAFETY ANALYSIS; SIMULATION
- Descriptors DEC
- ACCIDENTS; CONTAINMENT; COOLING SYSTEMS; HEAVY WATER COOLED REACTORS; HEAVY WATER MODERATED REACTORS; NATURAL URANIUM REACTORS; PHWR TYPE REACTORS; POWER REACTORS; PRESSURE TUBE REACTORS; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTOR PROTECTION SYSTEMS; REACTORS; SHUTDOWN; SYSTEM FAILURE ANALYSIS; SYSTEMS ANALYSIS; THERMAL REACTORS
Optional Information
- Notes
- 3 refs. Imprint:Proceedings published in two parts.