Safety related states identification in nuclear power plant with VVER reactors based on the objective probabilistic assessment
Description
A probabilistic assessment method for identification of safety related states during normal operation of a reactor unit is described. The applicability of this method is illustrated on the case of an abrupt loss of load (detachment from external grid) of the two Dukovany turbogenerators at the rated power level. Application of this universal method during the operation of nuclear power plants will enable such events or states to be identified as are not covered by intervention of the protective systems (steam generator tube rupture, partial break of the main steam or feedwater line, uncontrolled opening of safety valves). Early identification of safety related states at the reactor unit will facilitate control room personnel's decision-making and (after manual reactor tripping), intervention into the emergency rules
Additional details
Publishing Information
- Journal Title
- Bezpecnost Jaderne Energie
- Journal Volume
- 6
- Journal Issue
- 11-12
- Journal Page Range
- p. 367-369
- ISSN
- 1210-7085
INIS
- Country of Publication
- Czech Republic
- Country of Input or Organization
- Czech Republic
- INIS RN
- 30011819
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Translation
- Descriptors DEI
- DUKOVANY-1 REACTOR; EXPERT SYSTEMS; OUTAGES; POWER LOSSES; PROBABILISTIC ESTIMATION; REACTOR OPERATION; REACTOR SAFETY; RISK ASSESSMENT
- Descriptors DEC
- ENRICHED URANIUM REACTORS; OPERATION; POWER REACTORS; PWR TYPE REACTORS; REACTORS; SAFETY; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS; WWER TYPE REACTORS
Optional Information
- Notes
- English translation is available from Nuclear Information Center, 156 16 Prague-Zbraslav, Czech Republic, at USD 10.- per standard page (1800 characters)