Statistical learning and inverse uncertainty quantification in nuclear thermal-hydraulic simulation: application to the condensation modelling at the safety injection
Description
The BEPU (Best Estimate Plus Uncertainty) methodology is based on the validation and the uncertainty quantification of the physical models used in the nuclear computer codes. Having a robust methodology to calibrate a physical model, validate it and quantify its uncertainty is a major challenge. Therefore, the objective of this thesis is to develop methodologies for the validation and uncertainties quantification and apply them to the practical case of the condensation model at the Emergency Core Cooling (ECC) system. The first step was the development of a new Bayesian framework for the calibration and inverse uncertainty quantification of physical models using a multiplicative model uncertainty. The second step was a detailed thermohydraulic analysis of the experimental data in order to improve the physical understanding of the ECC condensation in the cold leg of a pressurised water reactor during a Loss Of Coolant Accident (LOCA). Two types of condensations occur in the cold leg: the condensation at the ECC and the condensation downstream the jet. The temperature at the outlet of the cold leg, and therefore at the entrance of the reactor's core, depends on these two models. The Bayesian framework is applied to calibrate a new condensation model at the ECC. This model has been validated and the uncertainties have been quantified. In the last step, an extension of the CIRCE methodology (called CIRCE 2-Steps) was developed. CIRCE is a methodology to determine the model uncertainty based on the difference between the experimental and calculated value of a quantity of interest. The proposed extension improves the estimation of the uncertainties of several models combined together and interacting on the same output variable, such as the temperature at the end of the cold leg. (author)
Abstract (French)
La methodologie BEPU (Best Estimate Plus Uncertainty) repose sur la validation et la quantification des incertitudes des modeles physiques utilises dans les codes de calcul nucleaires. Disposer d'une methodologie robuste permettant de caler un modele physique, de le valider et d'en quantifier les incertitudes est un enjeu majeur. Cette these a donc comme objectif de developper des methodologies pour la validation et la quantification d'incertitudes appliquees au cas pratique du modele de condensation a l'Injection de Securite (IS). La premiere etape a ete le developpement d'un nouveau cadre bayesien pour la calibration et la quantification inverse de l'incertitude des modeles physiques en utilisant une incertitude de modele multiplicative. La deuxieme etape a ete une analyse thermohydraulique detaillee des donnees experimentales afin d'ameliorer la comprehension physique de la condensation a l'IS dans la branche froide d'un reacteur a eau pressurisee lors d'un Accident de Perte de Refrigerant Primaire (APRP). Pendant cet accident, deux types de condensation surviennent dans la branche froide: la condensation a l'IS et la condensation en aval du jet. La temperature en sortie de la branche froide, et donc a l'entree du coeur du reacteur, depend de ces deux modeles. Le cadre bayesien est applique afin de calibrer un nouveau modele de condensation a l'IS. Ce modele a ete valide et ses incertitudes ont ete quantifiees. Dans la derniere etape, une extension de la methodologie CIRCE (appelee CIRCE 2-Steps) a ete developpee. CIRCE est une methodologie pour determiner l'incertitude du modele basee sur la difference entre la valeur experimentale et la valeur calculee d'une quantite d'interet. L'extension proposee ameliore l'estimation des incertitudes de plusieurs modeles combines entre eux et qui interagissent sur la meme variable de sortie, comme la temperature en sortie de la branche froide
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Additional details
Additional titles
- Original title (English)
- Apprentissage statistique et quantification inverse des incertitudes en simulation thermohydraulique nucleaire: application a la modelisation de la condensation a l'injection de securite
Publishing Information
- Imprint Pagination
- 89 p.
- Report number
- FRCEA-TH--16021
INIS
- Country of Publication
- France
- Country of Input or Organization
- France
- INIS RN
- 54039641
- Subject category
- S97: MATHEMATICAL METHODS AND COMPUTING; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S42: ENGINEERING;
- Resource subtype / Literary indicator
- Thesis
- Descriptors DEI
- CALIBRATION; COMPUTER CODES; COMPUTERIZED SIMULATION; DATA COVARIANCES; LOSS OF COOLANT; PWR TYPE REACTORS; REACTOR CORES; THERMAL HYDRAULICS; VALIDATION
- Descriptors DEC
- ACCIDENTS; ENRICHED URANIUM REACTORS; FLUID MECHANICS; HYDRAULICS; MECHANICS; POWER REACTORS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTORS; SIMULATION; TESTING; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 74 refs.; Available from the INIS Liaison Officer for France, see the INIS website for current contact and E-mail addresses