ISP-47 'containment thermal-hydraulics': lessons learned from MELCOR calculations
Creators
- 1. Ustav jaderneho vyzkumu Rez (UJV) CZ-25068 Rez (Czech Republic)
Description
Full text of publication follows: In 2002, OECD launched the 47. International Standard Problem (ISP 47) focused on some thermal hydraulic aspects of accident progression, namely on steam condensation and lighter-than-air gas behavior in containment of a nuclear power plant. The first step of the project (2002-2003) consisted of experiments performed on the French TOSQAN and MISTRA facilities, and benchmark calculations with various lumped-parameter or CFD codes. Nuclear Research Institute (UJV) participated in the ISP 47 with the lumped-parameter MELCOR code. The first UJV calculations (performed in 2003 and submitted to ISP 47) did not agree very well with Step-1 experiments, especially in case of large steam injection. Therefore, new calculations were performed in 2004 with the aim to identify possible reasons of discrepancies. It was found that the choice of a flow type around walls (INTERNAL or EXTERNAL) contributes significantly to the pressure overestimation in case of large steam injection. Even if the condensing surface is INSIDE a vessel, the calculations with EXTERNAL option were much closer to the experimental results. Other parameters had only limited influence (if any) on the results. Several types of nodalization were also tested and the results are discussed. The lessons learned from these sensitivity and nodalization studies may be useful for future calculations of other experiments where thermal-hydraulics play an important role (e.g. aerosol behavior). Applicability of results to calculations of prototype VVER containments is discussed, too. (author)
Availability note (English)
Available in abstract form only, full text entered in this recordAdditional details
Publishing Information
- Imprint Pagination
- 1 p.
- Report number
- INIS-FR--3347
Conference
- Title
- 11. international topical meeting on nuclear reactor thermal hydraulics (Nureth 11)
- Dates
- 2-6 Oct 2005
- Place
- Avignon (France)
INIS
- Country of Publication
- France
- Country of Input or Organization
- France
- INIS RN
- 36038708
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS; S42: ENGINEERING;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- COMPUTERIZED SIMULATION; CONTAINMENT BUILDINGS; FLOW MODELS; M CODES; MESH GENERATION; REACTOR ACCIDENTS; STEAM INJECTION; THERMAL HYDRAULICS; VAPOR CONDENSATION; WWER TYPE REACTORS
- Descriptors DEC
- ACCIDENTS; BUILDINGS; COMPUTER CODES; CONTAINMENT; ENRICHED URANIUM REACTORS; FLUID INJECTION; FLUID MECHANICS; HYDRAULICS; MATHEMATICAL MODELS; MECHANICS; POWER REACTORS; PWR TYPE REACTORS; REACTORS; SIMULATION; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS