Post-test calculation and uncertainty analysis of the experiment Quench-07 with the system code Athlet-CD
Creators
- 1. Gesellschaft fur Anlagen- und Reaktorsicherheit (GRS) mbH, Forschungsinstitute, Garching (Germany)
Description
In the frame of developmental assessment and code validation, a post-test calculation of the test QUENCH-07 was performed with ATHLET-CD. The system code ATHLET-CD is being developed for best-estimate simulation of accidents with core degradation and for evaluation of accident management procedures. It applies the detailed models of the thermal-hydraulic code ATHLET in an efficient coupling with dedicated models for core degradation and fission products behaviour. The first step of the work was the simulation of the test QUENCH-07 applying the modelling options recommended in the code User's Manual (reference calculation). The global results of this calculation showed a good agreement with the measured data. This calculation was complemented by a sensitivity analysis in order to investigate the influence of a combined variation of code input parameters on the simulation of the main phenomena observed experimentally. Results of this sensitivity analysis indicate that the main experimental measurements lay within the uncertainty range of the corresponding calculated values. Among the main contributors to the uncertainty of code results are the heat transfer coefficient due to forced convection to superheated steam-argon mixture, the thermal conductivity of the shroud isolation and the external heater rod resistance. Uncertainties on modelling of B4C oxidation do not affect significantly the total calculated hydrogen release rates. (authors)
Additional details
Publishing Information
- Publisher
- Organisation for Economic Co-Operation and Development - Nuclear Energy Agency - Committee on the Safety of Nuclear Installations
- Imprint Place
- Paris (France)
- Imprint Title
- Evaluation of uncertainties in relation to severe accidents and level-2 probabilistic safety analysis
- Imprint Pagination
- 1002 p.
- Journal Page Range
- p. 450-493
Conference
- Title
- Workshop proceedings evaluation of uncertainties in relation to severe accidents and level-2 probabilistic safety analysis
- Dates
- 7-9 Nov 2005
- Place
- Aix-en-Provence (France)
INIS
- Country of Publication
- France
- Country of Input or Organization
- Nuclear Energy Agency of the OECD (NEA)
- INIS RN
- 39033930
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS; S42: ENGINEERING; S37: INORGANIC, ORGANIC, PHYSICAL AND ANALYTICAL CHEMISTRY;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- A CODES; BORON CARBIDES; CHEMICAL REACTION KINETICS; COMPUTERIZED SIMULATION; DATA COVARIANCES; FISSION PRODUCT RELEASE; FUEL ELEMENT CLUSTERS; HYDROGEN; LOSS OF COOLANT; MULTIPLICATION FACTORS; OXIDATION; PROBABILISTIC ESTIMATION; QUENCHING; SENSITIVITY ANALYSIS; TEMPERATURE DISTRIBUTION; TEST FACILITIES; THERMAL HYDRAULICS; VALIDATION; ZIRCALOY
- Descriptors DEC
- ACCIDENTS; ALLOYS; BORON COMPOUNDS; CALCULATION METHODS; CARBIDES; CARBON COMPOUNDS; CHEMICAL REACTIONS; COMPUTER CODES; DIMENSIONLESS NUMBERS; ELEMENTS; FLUID MECHANICS; FUEL ASSEMBLIES; HYDRAULICS; KINETICS; MECHANICS; NONMETALS; REACTION KINETICS; REACTOR ACCIDENTS; SIMULATION; TESTING; TRANSITION ELEMENT ALLOYS; ZIRCONIUM ALLOYS; ZIRCONIUM BASE ALLOYS
Optional Information
- Notes
- 15 refs.