Evaluation of Efficiency of Passive Heat Removal System in VVER-1200 Under Beyond Design Basis Accidental Conditions
- 1. Scientific and Engineering Centre for Nuclear and Radiation Safety (SEC NRS), Moscow (Russian Federation)
Description
The paper presents the results of the steam generators passive heat removal system (PHRS) efficiency independent estimation for the NPP unit with a VVER-1200 reactor of the V-491 project during beyond design basis accidents. In SEC NRS the full-scale calculation model of the water-type passive heat removal system from a steam generator was developed and was implemented in the VVER - 1200 reactor (V-491) calculation model. All models were developed by using the best estimate code ATHLET (GRS, Germany). Since PHRS is an innovative safety system, the independent confirmation of its effectiveness in a wide range of emergency modes is especially important issue. PHRS is able to remove the heat from the reactor core due to the natural circulation of the coolant for a long period of time during beyond design basis accidents including the case of NPP station blackout. The paper contains a brief description of the PHRS and its calculation model, as well as the results of independent calculation analysis of the beyond design basis accidents, confirming the efficiency of PHRS. The paper demonstrates the possibility technical support organization of the Russian nuclear regulation authority (Rostechnadzor) to carry out its own independent scientific and technical assessments during licensing process of innovative reactor designs and this complies with the provisions of the IAEA Safety Standards Series Nos GSR Part 4 and GSG-13.
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Additional details
Identifiers
Publishing Information
- Imprint Place
- Vienna (International Atomic Energy Agency (IAEA))
- ISBN
- 978-92-0-103825-8
- Imprint Pagination
- 8 p.
- Series
- Proceeding Series
- ISSN
- 0074-1884
- Report number
- STI/PUB/2108
Conference
- Title
- International Conference on Topical Issues in Nuclear Installation Safety: Strengthening Safety of Evolutionary and Innovative Reactor Designs
- Dates
- 18-21 October 2022
- Place
- Vienna (Austria)
INIS
- Country of Publication
- International Atomic Energy Agency (IAEA)
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- AFTER-HEAT REMOVAL; BEYOND-DESIGN-BASIS ACCIDENTS; EFFICIENCY; GRS; IAEA; NATURAL CONVECTION; NUCLEAR POWER PLANTS; REACTOR CORES; REACTOR DESIGN; REGULATIONS; RHR SYSTEMS; SAFETY ANALYSIS; STATION BLACKOUT; STEAM GENERATORS; STEAM SYSTEMS; WWER TYPE REACTORS
- Descriptors DEC
- ACCIDENTS; BOILERS; CONVECTION; COOLING SYSTEMS; DESIGN; ENERGY SYSTEMS; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; HEAT TRANSFER; INTERNATIONAL ORGANIZATIONS; LAWS; MASS TRANSFER; NUCLEAR FACILITIES; POWER PLANTS; POWER REACTORS; PWR TYPE REACTORS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTOR LIFE CYCLE; REACTORS; REMOVAL; THERMAL POWER PLANTS; THERMAL REACTORS; VAPOR GENERATORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 5 refs., 12 figs.
- Secondary number(s)
- IAEA-CN--308(SUPPLEMENTARY FILES)