Analysis of GDH blockage event at ignalina NPP
- 1. Lithuanian Energy Inst., Kaunas (Lithuania)
Description
The paper presents analysis of the postulated blocking of coolant flow rate in Group Distribution Header event at Ignalina NPP. Two types of analysis-'best estimate' and 'partially-conservative' are performed. Best-estimate' approach is based on the best estimate codes with realistic boundary and initial conditions plus uncertainty analysis, while partially-conservative' approach - on the best estimate codes with conservative boundary and initial conditions plus conservative assumptions. The performed comparison of both calculations show that the peak fuel cladding temperatures for 'best-estimate' calculation taking into account the uncertainty analysis is slightly lower in comparison with partially-conservative' calculation. 'Partially-conservative' approach requires considerably less computational time. However, when with this methodology obtained results do not meet acceptance criteria (as it was in this particular case), the complete analysis by employing 'best-estimate' approach is necessary. (author)
Additional details
Publishing Information
- Publisher
- Japan Society of Mechanical Engineers
- Imprint Place
- Tokyo (Japan)
- Imprint Title
- ICONE-11: Proceedings of the 11th international conference on nuclear engineering
- Imprint Pagination
- [3610 p.]
- Journal Page Range
- [8 p.]
Conference
- Title
- 11. international conference on nuclear engineering
- Acronym
- ICONE-11
- Dates
- 20-23 Apr 2003
- Place
- Tokyo (Japan)
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 35045205
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- CIRCULATING SYSTEMS; COOLANTS; FLOW RATE; FUEL CANS; FUEL ELEMENTS; HYDRAULICS; IGNALINA-1 REACTOR; NUCLEAR POWER PLANTS; PUMPS; REACTOR ACCIDENTS; REACTOR COOLING SYSTEMS; REACTOR SAFETY; SAFETY ANALYSIS; TWO-PHASE FLOW
- Descriptors DEC
- ACCIDENTS; COOLING SYSTEMS; ENERGY SYSTEMS; ENRICHED URANIUM REACTORS; EQUIPMENT; FLUID FLOW; FLUID MECHANICS; GRAPHITE MODERATED REACTORS; LWGR TYPE REACTORS; MECHANICS; NUCLEAR FACILITIES; POWER PLANTS; POWER REACTORS; REACTOR COMPONENTS; REACTORS; SAFETY; THERMAL POWER PLANTS; THERMAL REACTORS; WATER COOLED REACTORS
Optional Information
- Notes
- This CD-ROM can be used for WINDOWS 9x/NT/2000/ME/XP, MACINTOSH; Acrobat Reader is included; Data in PDF format, Track No. 07, Session 7-28, ICONE-36170