Bleed and feed studies to assess the development of emergency operating procedures for VVER-type reactors
Creators
- 1. KFKI Atomic Energy Research Inst., Budapest (Hungary). Thermalhydraulic Dept.
Description
At present, no systematic accident management has been implemented in Paks NPP of VVER-440/213-type nuclear power plant. However, results of the safety reassessment of the Paks NPP showed that one group of the measures to enhance the safety is the modernization of emergency operating procedures, including the implementation of accident management. Report is based on experimental results obtained on the PMK-2, an integral-type facility of the Paks NPP. The purpose is to study the application of secondary and primary side bleed and feed procedures to prevent the core damage for beyond DBA accident sequences. Report contains items as: assessment of the effectiveness of the operator interventions; performing accident management analyses for the PMK-2 facility; experimental results on the accident scenarios selected; computer code verification; assessment of the applied procedures
Additional details
Publishing Information
- Publisher
- American Society of Mechanical Engineers.
- Imprint Place
- New York, NY (United States)
- ISBN
- 0-7918-1226-X
- Imprint Title
- ICONE-4: Proceedings. Volume 3: Safety and reliability
- Imprint Pagination
- 595 p.
- Journal Page Range
- p. 511-516.
Conference
- Title
- ASME/JSME international conference on nuclear engineering.
- Acronym
- ICONE 4
- Dates
- 10-13 Mar 1996.
- Place
- New Orleans, LA (United States).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 27063099
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- DATA; EMERGENCY PLANS; MANAGEMENT; MITIGATION; MODIFICATIONS; PAKS-1 REACTOR; PAKS-2 REACTOR; PAKS-3 REACTOR; PAKS-4 REACTOR; REACTOR ACCIDENTS; SAFETY ANALYSIS; TEST FACILITIES
- Descriptors DEC
- ACCIDENTS; ENRICHED URANIUM REACTORS; INFORMATION; POWER REACTORS; PWR TYPE REACTORS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS; WWER TYPE REACTORS
Optional Information
- Secondary number(s)
- CONF-960306--.