Assessment of hydrogen risk using advanced methodology for lumped parameter code-MELCOR
Creators
- 1. Nuclear Power and Safety Division, Nuclear Research Institute Rez plc., Husinec (Czech Republic)
Description
The hydrogen risk is one of the most important containment integrity challenge during a severe accident progression at the VVER type reactors installed at the Czech NPPs. On the basis of recent comprehensive research results the general flame acceleration (FA) and deflagration-to-detonation transition (DDT) criteria were formulated. The main objective of the new methodology developed in the NRI Rez was to prepare an analytical tool for the assessment of the hydrogen risk at the Czech NPPs in the course of a severe accident and also for the design of hydrogen removal system which should be able to prevent or at least minimize the threats of hydrogen detonation in containments. The major idea on which the development of models for the FA and DDT criteria was based is described in OECD state-of-art report (NEA, 2000). The module for the computation of FA criterion (often named σ-criterion) and DDT one (also named λ or Dorofeev criterion) was linked to the MELCOR 1.8.5 model of VVER-1000 containment. The most important feature of new model is that it makes possible to evaluate the both of the criteria for all compartments in the containment continuously during severe accident scenario progression. The containment model, which could be used for such a calculation, has to be very detailed owing to appropriate description of hydrogen distribution. New model was tested by calculation of hydrogen detonation risk in the VVER-1000 containment during severe accident scenario initiated by medium break LOCA. At present two more VVER-1000 severe accident scenarios have been analyzed. The mapping of a hydrogen detonation risk in individual compartments inside containment was performed. The results of analysis confirm that the risk of hydrogen detonation in the great majority of containment compartments during severe accidents is very high if the hydrogen removal system is not installed. (author)
Availability note (English)
Available from Japan Society of Mechanical Engineers, 35 Shinanomachi, Shinjuku-ku, Tokyo 160-0016, JapanAdditional details
Publishing Information
- Publisher
- Japan Society of Mechanical Engineers
- Imprint Place
- Tokyo (Japan)
- Imprint Title
- Proceedings of the ICONE-15 (Revised). The 15th international conference on nuclear engineering
- Imprint Pagination
- [3174 p.]
- Journal Page Range
- [6 p.]
Conference
- Title
- 15. international conference on nuclear engineering
- Acronym
- ICONE-15
- Dates
- 22-26 Apr 2007
- Place
- Nagoya, Aichi (Japan)
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 39048704
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- COMBUSTION; COMPUTERIZED SIMULATION; CONTAINMENT; EXPLOSIONS; FLAME PROPAGATION; HYDROGEN; LOSS OF COOLANT; M CODES; NUCLEAR POWER PLANTS; REACTOR ACCIDENTS; RISK ASSESSMENT; WWER TYPE REACTORS
- Descriptors DEC
- ACCIDENTS; CHEMICAL REACTIONS; COMPUTER CODES; ELEMENTS; ENRICHED URANIUM REACTORS; NONMETALS; NUCLEAR FACILITIES; OXIDATION; POWER PLANTS; POWER REACTORS; PWR TYPE REACTORS; REACTOR ACCIDENTS; REACTORS; SIMULATION; THERMAL POWER PLANTS; THERMAL REACTORS; THERMOCHEMICAL PROCESSES; WATER COOLED REACTORS; WATER MODERATED 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, Folder Name Final Paper, Paper ID ICONE15-10431.pdf; 6 refs., 3 figs., 2 tabs.