Uncertainty quantification of isotopic densities in depleted fuel
| العنوان: | Uncertainty quantification of isotopic densities in depleted fuel |
|---|---|
| المؤلفون: | Lahaye, S., Luo, J., Bellier, P., Huynh, Td., Tsilanizara, A. |
| المساهمون: | CEA-Direction des Energies (ex-Direction de l'Energie Nucléaire) (CEA-DES (ex-DEN)), Commissariat à l'énergie atomique et aux énergies alternatives (CEA), amplexor, amplexor |
| المصدر: | ANS Best Estimate Plus Uncertainty International Conference (BEPU 2018) ANS Best Estimate Plus Uncertainty International Conference (BEPU 2018), May 2018, Lucca, Italy |
| بيانات النشر: | HAL CCSD, 2018. |
| سنة النشر: | 2018 |
| مصطلحات موضوعية: | [PHYS.NUCL] Physics [physics]/Nuclear Theory [nucl-th], Depletion, [PHYS.NUCL]Physics [physics]/Nuclear Theory [nucl-th], [PHYS.NEXP] Physics [physics]/Nuclear Experiment [nucl-ex], PWR, Fuel Cycle, PIE, Uncertainty Quantification, [PHYS.NEXP]Physics [physics]/Nuclear Experiment [nucl-ex] |
| الوصف: | International audience; Uncertainty quantification of interest outputs based on the nuclear data is an importantissue for nuclear safety, from operation of nuclear facilities to long termdeposit management. To be complete, the Verification and Validation process musttake into account the uncertainty quantification due to various sources input data,design, models...This work focuses on the VVUQ process for depletion code systems on a PWRfuel rod application. We compare the results of two CEA depletion code systems(namely DARWIN/PEPIN2.4 and MENDEL v1.2) and experimental data. Experimentaldata reported by a 2008 paper from Dr. Sasahara gives isotopic concentrationfor four UO2 fuel samples irradiated up to 64.7 MWd/t in a pressurized waterreactor. Nuclear data nominal data and uncertainties on decay data are taken fromthe JEFF-3.1.1, when uncertainties on cross section data are chosen from the CEACOMAC data base.Concerning the choice of uncertainty quantification methods, DARWIN/PEPIN2deterministic approach is based on sensitivity profiles computation by direct forwardperturbation, thanks to INCERD module. MENDEL probabilistic method isbased on Monte Carlo correlated sampling. Those samplings are achieved throughthe CEA uncertainty platform URANIE.Experimental measurement errors and nuclear input data uncertainties are taken intoaccount, when modelisation biases or algorithm accuracy are supposed negligible.Output quantities of interest are the isotopic concentrations at given times.We show that both uncertainty propagation results give similar results, compatiblewith experimental data and validating both the methods and both code systems onthis application. We focus on the elaboration of a measure for sensibility coefficientsapplicable to the stochastic approach, where thousands of eventually correlateduncertain input parameters are taken into account. |
| وصف الملف: | application/pdf |
| اللغة: | English |
| URL الوصول: | https://explore.openaire.eu/search/publication?articleId=dedup_wf_001::6d6c53457f9c98fde5f9bd7ff0dc187f https://hal.science/hal-02415484 |
| حقوق: | OPEN |
| رقم الأكسشن: | edsair.dedup.wf.001..6d6c53457f9c98fde5f9bd7ff0dc187f |
| قاعدة البيانات: | OpenAIRE |
| الوصف غير متاح. |