The examination of the vulnerability of NPP-Cernavoda to a severe accident due to the loss of the entire electrical power supply
Creators
- 1. Nuclear Savety Department, Center of Technology and Engineering for Nuclear Projects, PO Box 5204 MG-04, R-76900 Bucuresti (Romania)
Description
In this paper it is presented the framework for the PSA Level 2 analysis, where it is selected one of the worst severe accident sequence, such as that initiated from the loss of all electrical power sources SBO (Station Blackout). To examine the vulnerability of NPP-Cernavoda to this severe accident sequence, a complete quantitative analysis is done by using the specialized severe accident code MAAP-WS for NPP CANDU-600. The main result of this analysis is that even if the containment fails, the release of fission products to environment is very low, except the noble gases. An accident recovery can be obtained if we consider the dousing system available initially. Also the course of the accident can be changed if we follow-up the sequences' pathway given in the event trees for containment. (author) 10 figs., 1 tab., 5 refs
Availability note (English)
Available from authors by request.Additional details
Publishing Information
- Publisher
- RENEL - Romanian Electricity Authority.
- Imprint Place
- Neptun-Olimp (Romania)
- Imprint Title
- CNE'96: National Energy Conference 'Improving Energy Efficiency in a Transition Economy'. Proceedings of Section IV: Nuclear Power
- Imprint Pagination
- 198 p.
- Journal Page Range
- p. 36-46.
Conference
- Title
- National Energy Conference 'Improving Energy Efficiency in a Transition Economy'.
- Acronym
- CNE'96
- Dates
- 1-5 Sep 1996.
- Place
- Neptun-Olimp (Romania).
INIS
- Country of Publication
- Romania
- Country of Input or Organization
- Romania
- INIS RN
- 28037631
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- CANDU TYPE REACTORS; CERNAVODA-1 REACTOR; ELECTRIC POWER; ENERGY LOSSES; M CODES; OUTAGES; POWER LOSSES; PROBABILISTIC ESTIMATION; REACTOR ACCIDENTS; RISK ASSESSMENT; SAFETY ANALYSIS; VULNERABILITY
- Descriptors DEC
- ACCIDENTS; COMPUTER CODES; HEAVY WATER COOLED REACTORS; HEAVY WATER MODERATED REACTORS; NATURAL URANIUM REACTORS; PHWR TYPE REACTORS; POWER; POWER REACTORS; PRESSURE TUBE REACTORS; REACTORS; THERMAL REACTORS
Optional Information
- Notes
- Imprint:Conference proceedings published in 8 sections.