Contribution to the development and the qualification of a calculation method for the management of PWR reactors, by means of the system NEPTUNE. Fessenheim-2 follow-up
Description
The aim of this study is the definition, from the NEPTUNE code system, of a neutron calculation scheme for the follow-up of pressurized water power reactors and its application to the Fessenheim-2 follow-up. First, a description of the Fessenheim reactor core and of the fission chamber which have been used for the measurements of activity in the instrumented assemblies is given, and some theoretical points on the codes and calculation methods are recalled. Then, one presents a sensitivity analysis for the choice of a calculation scheme and the calculation of an activity map of the new core without evolution. The results needed to analyze the first cycle are given. These results are obtained after the calculation of evolution using the evolutive variation-data collections, which allow to take into account feedback (Doppler effect, due to the fuel temperature variation, and effect due to the moderator temperature variation). Finally, the calculation results of the beginning of the second cycle are given.
Abstract (French)
L'objectif de cette etude est la definition, a partir du systeme de codes NEPTUNE, d'un schema de calcul neutronique actualise pour le suivi des reacteurs de puissance a eau legere pressurisee et son application au suivi du coeur du reacteur FESSENHEIM 2. Le chapitre I presente une description du coeur Fessenheim et de la chambre de fission qui a ete utilisee pour les mesures d'activites dans les assemblages instrumentes et quelques rappels theoriques sur les codes et les methodes de calculs. Le chapitre II expose une etude de sensibilite pour le choix d'un schema de calcul et le calcul d'une carte d'activite sur le coeur neuf sans evolution. Le chapitre III donne l'ensemble des resultats necessaires au depouillement du premier cycle. Ces resultats sont obtenus a la suite de calcul d'evolution utilisant des bibliotheques evolutives a variations, qui permettent de prendre en compte les contre-reactions (effet Doppler, du au changement de temperature du combustible, et effet du a la variation de la temperature du moderateur). Le chapitre IV donne les resultats de calcul en debut de deuxieme cycle.Files
55006269.pdf
Files
(9.2 MB)
| Name | Size | Download all |
|---|---|---|
|
md5:8f61742da49968c08acdf4b95935c675
|
9.2 MB | Preview Download |
Additional details
Additional titles
- Original title (French)
- Contribution a l'elaboration et a la qualification d'un schema de calcul pour la gestion des reacteurs PWR, a l'aide du systeme Neptune. Suivi du reacteur Fessenheim-2
Publishing Information
- Imprint Pagination
- 288 p.
- Report number
- FRCEA-TH--16589
INIS
- Country of Publication
- France
- Country of Input or Organization
- France
- INIS RN
- 55006269
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Thesis
- Descriptors DEI
- A CODES; B CODES; BURNABLE POISONS; BURNUP; COMPUTER CALCULATIONS; CROSS SECTIONS; D CODES; FEEDBACK; FESSENHEIM-2 REACTOR; FINITE ELEMENT METHOD; FISSION CHAMBERS; FUEL ASSEMBLIES; FUEL MANAGEMENT; MAPS; NEUTRON FLUX; NEUTRON REFLECTORS; NEUTRON TRANSPORT; NUCLEAR DATA COLLECTIONS; POWER DISTRIBUTION; PWR TYPE REACTORS; REACTIVITY; REACTOR CORES; SENSITIVITY ANALYSIS; SPATIAL DISTRIBUTION; TEMPERATURE DEPENDENCE; THREE-DIMENSIONAL CALCULATIONS; TWO-DIMENSIONAL CALCULATIONS; URANIUM 235; WATER
- Descriptors DEC
- ACTINIDE NUCLEI; ALPHA DECAY RADIOISOTOPES; CALCULATION METHODS; COMPUTER CODES; DISTRIBUTION; ENRICHED URANIUM REACTORS; EVEN-ODD NUCLEI; HEAVY NUCLEI; HYDROGEN COMPOUNDS; INTERNAL CONVERSION RADIOISOTOPES; IONIZATION CHAMBERS; ISOMERIC TRANSITION ISOTOPES; ISOTOPES; MANAGEMENT; MATERIALS; MATHEMATICAL SOLUTIONS; MEASURING INSTRUMENTS; MINUTES LIVING RADIOISOTOPES; NEUTRAL-PARTICLE TRANSPORT; NEUTRON ABSORBERS; NEUTRON DETECTORS; NUCLEAR MATERIALS MANAGEMENT; NUCLEAR POISONS; NUCLEI; NUMERICAL SOLUTION; OXYGEN COMPOUNDS; POWER REACTORS; PWR TYPE REACTORS; RADIATION DETECTORS; RADIATION FLUX; RADIATION TRANSPORT; RADIOISOTOPES; REACTOR COMPONENTS; REACTOR MATERIALS; REACTORS; SPONTANEOUS FISSION RADIOISOTOPES; THERMAL REACTORS; URANIUM ISOTOPES; WATER COOLED REACTORS; WATER MODERATED REACTORS; YEARS LIVING RADIOISOTOPES
Optional Information
- Notes
- Available from the INIS Liaison Officer for France, see the INIS website for current contact and E-mail addresses; This record replaces 18076909