Objectives and status of the oecd/nea sub-group on uncertainty analysis in modelling (uam) for design, operation and safety analysis of sfrs (sfr-uam)
| العنوان: | Objectives and status of the oecd/nea sub-group on uncertainty analysis in modelling (uam) for design, operation and safety analysis of sfrs (sfr-uam) |
|---|---|
| المؤلفون: | Rimpault, G., Buiron, L., Stauff, N., Kim, TK., Taiwo, TA., Lee, Yk., Aures, A., Bostelmann, F., Fridman, E., Kereszturi, A., Batki, B., Kodeli, IA., Mikityuk, K., Lopez, R., Gomez, A., Puente-Espel, F., Del Valle, E., Peregudov, A., Semenov, M., Manturov, G., Nakahara, Y., Dyrda, J., Ivanova T, . |
| المساهمون: | amplexor, amplexor, CEA-Direction des Energies (ex-Direction de l'Energie Nucléaire) (CEA-DES (ex-DEN)), Commissariat à l'énergie atomique et aux énergies alternatives (CEA), Argonne National Laboratory [Lemont] (ANL), GRS, Paul Scherrer Institute (PSI), National Environment Agency [Singapore] (NEA) |
| المصدر: | International Conference on Fast Reactors and Related Fuel Cycles (FR-2017) International Conference on Fast Reactors and Related Fuel Cycles (FR-2017), Jun 2017, Kyoto, Japan International Conference on Fast Reactors and Related Fuel Cycles: Next Generation Nuclear Systems for Sustainable Development (FR17), 26.-29.06.2017, Yekaterinburg, Russian FederationProceedings of the International Conference on Fast Reactors and Related Fuel Cycles |
| بيانات النشر: | HAL CCSD, 2017. |
| سنة النشر: | 2017 |
| مصطلحات موضوعية: | [PHYS.NUCL] Physics [physics]/Nuclear Theory [nucl-th], SFR, [PHYS.NUCL]Physics [physics]/Nuclear Theory [nucl-th], [PHYS.NEXP] Physics [physics]/Nuclear Experiment [nucl-ex], [PHYS.NEXP]Physics [physics]/Nuclear Experiment [nucl-ex], uncertainties, OECD benchmark, reactivity coefficients |
| الوصف: | International audience; An OECD/NEA sub-group on Uncertainty Analysis in Modelling (UAM) for Design, Operation and Safety Analysis of Sodium-cooled Fast Reactors (SFR-UAM) has been formed under the NSC/WPRS/EGUAM and is currently undertaking preliminary studies after having specified a series of benchmarks. The incentive for launching the SFR-UAM task force comes from the desire to utilize current understanding of important phenomena to define and quantify the main core characteristics affecting safety and performance of SFRs. Best-estimate codes and data together with an evaluation of the uncertainties are required for that purpose, which challenges existing calculation methods. The group benefits from the results of a previous Sodium-cooled Fast Reactor core Feed-back and Transient response (SFR-FT) Task Force work under the NSC/WPRS/EGRPANS.Two SFR cores have been selected for the SFR-UAM benchmark, a 3600MWth oxide core and a 1000MWth metallic core. Their neutronic feedback coefficients are being calculated for transient analyses. The SFR-UAM sub-group is currently defining the grace period or the margin to melting available in the different accident scenarios and this within uncertainty margins.Recently, the work of the sub-group has been updated to incorporate new exercises, namely, a depletion benchmark, a control rod withdrawal benchmark, and the SUPER-PHENIX start-up transient. Experimental evidence in support of the studies is also being developed. |
| وصف الملف: | application/pdf |
| اللغة: | English |
| URL الوصول: | https://explore.openaire.eu/search/publication?articleId=dedup_wf_001::96f8f2f22660521d45d7474660e2d3e9 https://hal.science/hal-02419676 |
| حقوق: | OPEN |
| رقم الأكسشن: | edsair.dedup.wf.001..96f8f2f22660521d45d7474660e2d3e9 |
| قاعدة البيانات: | OpenAIRE |
| الوصف غير متاح. |