Validation of a BEPU methodology through a blind benchmark activity at the PKL test facility
Freixa et al. - 2019 - VALIDATION OF A BEPU METHODOLOGY THROUGH A BLIND BENCHMARK ACTIVITY AT THE PKL TEST FACILITY.pdf (1,414Mb) (Restricted access) Request copy
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Document typeConference report
PublisherAmerican Nuclear Society (ANS)
Rights accessRestricted access - publisher's policy
Validation is a key step in the field of thermal hydraulics and has played a crucial role in the implementation of system codes. These codes are then included in licensing methodologies being those either best estimate plus uncertainties (BEPU) or conservative approaches. However, only a small amount of efforts has been done on the validation of the methodologies as a whole. Such validation would imply the comparison of the bounding limits and the experimental data. Due to the lack of actual data of accidental situations, such validation should be carried out with data from integral test facility (ITF) experiments.The OECD/NEA PKL-4 test programme is investigating safety issues relevant for current pressurizedwater reactor (PWR) plants as well as for new PWR design concepts focusing on complex heat transfer mechanisms under two-phase flow. Within the project, a blind benchmark activity has been launched where an IBLOCA experiment has been simulated by 12 different organizations. The Universitat Politècnica de Catalunya(UPC) participated to the activity with a blind BEPU approach with the main objective to assess the validity of the methodology as a whole. At first, the acceptance criteria for the particular scenario have been evaluated. Secondly, in order to broaden the extend of the validation, the results of the different participants have been interpreted as if they were blind experiments as well. Finally, different output parameters have been considered providing a matrix of results that is used to evaluate the validity of the methodology.
CitationFreixa, J. [et al.]. Validation of a BEPU methodology through a blind benchmark activity at the PKL test facility. A: International Topical Meeting on Nuclear Reactor Thermal Hydraulics. "18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics: NURETH-18: Portland, USA: 18-23 August, 2019". La Grange Park: American Nuclear Society (ANS), 2019, p. 366-379.
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