WWER-1000/320 steam generator collector rupture. Radiological consequences
Description
A model describing a hypothetical accident with direct release of primary coolant to the atmosphere is proposed. Cover lifting of the primary collector due to a rupture of the fixing bolts leads to a coolant release. The initial and boundary conditions of the accident scenario have been selected to provide for the most unfavorable conditions. The total release of primary coolant during the first 15 min of transient are estimated to 50.8 tons, of these 48.5 t with the initial activity in the primary coolant circuit. Without evacuation or sheltering, after 7 days of exposure, the expected dose at the boundary of the restricted zone is 0.0182 Sv for the whole body and 0.184 Sv for the thyroid gland. The effective equivalent dose on the site would be 0.0521 Sv. As a result of the analysis it is concluded that the steam generator collector rupture is not jeopardizing the core heat removal even with a minimum configuration of ECCS as the cooling is accomplished through the steam generators. The radiological consequences of the accident would be relatively small if an emergency procedure is applied at the 15-th minute of the transient. 1 ref
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Additional details
Publishing Information
- Imprint Title
- Proceedings of a scientific-technical conference dedicated to the 20-th anniversary of Kozloduy NPP with international participation
- Imprint Pagination
- 442 p.
- Journal Page Range
- p. 247-251.
- Report number
- INIS-BG--0013
Conference
- Title
- Scientific-technical conference dedicated to the 20-th anniversary of Kozloduy NPP with international participation.
- Dates
- 25-26 Oct 1994.
- Place
- Kozloduy (Bulgaria).
INIS
- Country of Publication
- Bulgaria
- Country of Input or Organization
- Bulgaria
- INIS RN
- 28033974
- Subject category
- S61: RADIATION PROTECTION AND DOSIMETRY; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- ECCS; FAILURES; LOSS OF COOLANT; PRIMARY COOLANT CIRCUITS; RADIATION DOSES; REACTOR CONTROL SYSTEMS; STEAM GENERATORS; SYSTEM FAILURE ANALYSIS; WWER-5 REACTOR
- Descriptors DEC
- ACCIDENTS; BOILERS; CONTROL SYSTEMS; COOLING SYSTEMS; ENGINEERED SAFETY SYSTEMS; ENRICHED URANIUM REACTORS; POWER REACTORS; PWR TYPE REACTORS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTOR PROTECTION SYSTEMS; REACTORS; SYSTEMS ANALYSIS; THERMAL REACTORS; VAPOR GENERATORS; WATER COOLED REACTORS; WATER MODERATED REACTORS; WWER TYPE REACTORS