Correlations between nuclear data and results of integral slab experiments. Case of hafnium
Description
The aim of this thesis was to evaluate how much integral slab experiments can both reduce discrepancies between experimental results and calculations, and improve the knowledge of hafnium isotopes neutronic parameters by an adapted sensitivity and uncertainty method. A statistical approach, based on the generalized least squares method and perturbation theory, has been incorporated into our calculation system in order to deduce microscopic cross-section adjustments from observed integral measurements on this particular 'mock-up' reactor. In this study it has been established that the correlations between integral parameters and hafnium capture cross-sections enable specific variations in the region of resolved resonances at the level of multigroup and punctual cross-sections recommended data (JEF-2.2 evaluation) to be highlighted. The use of determinist methods (APOLLO2 code) together with Monte Carlo- type simulations (TRIPOLI4 code) enabled a depth analysis of the modelling approximations to be carried out. Furthermore, the sensitivity coefficient validation technique employed leads to a reliable assessment of the quality of the new basic nuclear data. In this instance, the adjustments proposed for certain isotope 177Hf resonance parameters reduce, after error propagation, by 3 to 5 per cent the difference between experimental results and calculations related to this absorbent's efficiency. Beyond this particular application, the qualification methodology integrated in our calculation system should enable other basic sizing parameters to be treated (chemical / geometric data or other unexplored nuclear data) to make technological requirements less stringent. (author)
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Additional details
Additional titles
- Original title (French)
- Correlations entre donnees nucleaires et experiences integrales a plaques: le cas du hafnium
Publishing Information
- Imprint Pagination
- 362 p.
- Report number
- FRCEA-TH--725
INIS
- Country of Publication
- France
- Country of Input or Organization
- France
- INIS RN
- 30044362
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Resource subtype / Literary indicator
- Thesis
- Descriptors DEI
- A CODES; ACCURACY; BURNABLE POISONS; COMPUTERIZED SIMULATION; DATA COVARIANCES; HAFNIUM; INTEGRAL CROSS SECTIONS; LEAST SQUARE FIT; MATERIAL BUCKLING; MONTE CARLO METHOD; MULTI-PARAMETER ANALYSIS; NEUTRON TRANSPORT; NUCLEAR DATA COLLECTIONS; PERTURBATION THEORY; RESONANCE; RESONANCE INTEGRALS; T CODES
- Descriptors DEC
- BUCKLING; CALCULATION METHODS; COMPUTER CODES; CROSS SECTIONS; ELEMENTS; INTEGRALS; MATERIALS; MAXIMUM-LIKELIHOOD FIT; METALS; NEUTRAL-PARTICLE TRANSPORT; NEUTRON ABSORBERS; NUCLEAR POISONS; NUMERICAL SOLUTION; RADIATION TRANSPORT; REACTOR MATERIALS; SIMULATION; TRANSITION ELEMENTS
Optional Information
- Notes
- 128 refs.