Code-experiment comparison on wall condensation tests in the presence of non-condensable gases—Numerical calculations for containment studies
Creators
- 1. Institut de Radioprotection et de Sûreté Nucléaire (IRSN), PSN-RES, SCA, BP 68, 91192 Gif-sur-Yvette (France)
Description
Highlights: ► Steam condensation on walls has been investigated in the TOSQAN vessel. ► Experiments on 7 different tests have been performed. ► Different steam injections and wall temperatures are used. ► Simulations are performed in 2D using the TONUS code. ► Code-experiments comparisons at many different locations show a good agreement. - Abstract: During the course of a severe Pressurized Water Reactor accident, pressurization of the containment occurs and hydrogen can be produced by the reactor core oxidation and distributed in the containment according to convection flows and wall condensation. Filmwise wall condensation in the presence of non-condensable gases is a subject of many interests and extensive studies have been performed in the past. Some empirical correlations have demonstrated their limit for extrapolation under different thermal-hydraulic conditions and at different geometries/scales. The French Institute for Radiological Protection and Nuclear Safety (IRSN) has developed a numerical tool and an experimental facility in order to investigate free convection flows in the presence of condensation. The objective of this paper is to present numerical results obtained on different wall condensation tests in 7 m3 volume vessel (TOSQAN facility), and to compare them with the experimental ones. Over eight tests are considered here, and code-experiment comparison is performed on many different locations, giving an extensive insight of the code assessment for air–steam mixture flows involving wall condensation in the presence of non-condensable gases.
Availability note (English)
Available from http://dx.doi.org/10.1016/j.nucengdes.2012.08.012Additional details
Identifiers
- DOI
- 10.1016/j.nucengdes.2012.08.012;
- PII
- S0029-5493(12)00443-8;
Publishing Information
- Journal Title
- Nuclear Engineering and Design
- Journal Volume
- 253
- Journal Page Range
- p. 98-113
- ISSN
- 0029-5493
- CODEN
- NEDEAU
INIS
- Country of Publication
- Netherlands
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 44025361
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S42: ENGINEERING;
- Descriptors DEI
- AIR; COMPARATIVE EVALUATIONS; COMPUTERIZED SIMULATION; CONTAINERS; CONTAINMENT; EXTRAPOLATION; HYDROGEN PRODUCTION; NATURAL CONVECTION; OXIDATION; PRESSURIZATION; PWR TYPE REACTORS; REACTOR ACCIDENTS; REACTOR CORES; STEAM; STEAM INJECTION; T CODES; THERMAL HYDRAULICS; VAPOR CONDENSATION; WALLS
- Descriptors DEC
- ACCIDENTS; CHEMICAL REACTIONS; COMPUTER CODES; CONVECTION; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; EVALUATION; FLUID INJECTION; FLUID MECHANICS; FLUIDS; GASES; HEAT TRANSFER; HYDRAULICS; MASS TRANSFER; MATHEMATICAL SOLUTIONS; MECHANICS; NUMERICAL SOLUTION; POWER REACTORS; REACTOR COMPONENTS; REACTORS; SIMULATION; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Copyright
- Copyright (c) 2012 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.