Effectiveness of a passive heat removal system for a new WWER reactor
- 1. Gesellschaft fur Reaktorsicherheit mbH, Forchungsgelande, Garching D-8046 (Germany)
- 2. Inst. Atomenergoprojekt, 7 Bakuninskaya Str., Moscow 107815 (USSR)
- 3. Kurchatov Atomic Energy Inst., 1 Kurchatov Square, Moscow 123182 (USSR)
Description
This paper reports on a new WWER-1000 reactor concept which is presently under development. The work is supported by the cooperation contract between SIEMENS and GRS with MINATOMENERGO. LOCA analyses under the assumption of total loss of alternating current power for a period of 24 h and considered measures for prevention and mitigation of core melting by means of passive systems were conducted. For the 1% small break two calculations were performed with the code ATHLET in order to investigate the effectiveness of a principally new passive heat removal system (PHRS) and of the accumulators. The calculations demonstrate that an additional time period of more than one hour can be gained if the PHRS power is increased from 2% to 3% related to the nominal thermal power
Additional details
Publishing Information
- Publisher
- American Nuclear Society.
- Imprint Place
- La Grange Park, IL (United States)
- ISBN
- 0-89448-150-9
- Imprint Title
- Proceedings of the fifth nuclear thermal hydraulics
- Imprint Pagination
- 492 p.
- Journal Page Range
- p. 369-376.
Conference
- Title
- Winter meeting of the American Nuclear Society (ANS) and nuclear power and technology exhibit.
- Dates
- 26-30 Nov 1989.
- Place
- San Francisco, CA (United States).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 24011731
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S61: RADIATION PROTECTION AND DOSIMETRY;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- A CODES; AFTER-HEAT REMOVAL; CALCULATION METHODS; LOSS OF COOLANT; MELTING; MITIGATION; PLANNING; REACTOR ACCIDENTS; REACTOR COOLING SYSTEMS; REACTOR CORES; REACTOR SAFETY; REACTOR SAFETY EXPERIMENTS; SAFETY ANALYSIS; SAFETY ENGINEERING; TESTING; WWER TYPE REACTORS
- Descriptors DEC
- ACCIDENTS; COMPUTER CODES; COOLING SYSTEMS; ENRICHED URANIUM REACTORS; PHASE TRANSFORMATIONS; POWER REACTORS; PWR TYPE REACTORS; REACTOR COMPONENTS; REACTORS; REMOVAL; SAFETY; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Secondary number(s)
- CONF-891103--.