| Application of the WCOBRA/TRAC best-estimate methodology to the AP600 large-break LOCA analysis J Zhang, SM Bajorek, RM Kemper, ME Nissley, N Petkov, LE Hochreiter Nuclear engineering and design 186 (1-2), 279-301, 1998 | 37 | 1998 |
| Development of good practice guidance for quantification of thermal-hydraulic code model input uncertainty J Baccou, J Zhang, P Fillion, G Damblin, A Petruzzi, R Mendizábal, ... Nuclear Engineering and Design 354, 110173, 2019 | 31 | 2019 |
| SAPIUM: A generic framework for a practical and transparent quantification of thermal-hydraulic code model input uncertainty J Baccou, J Zhang, P Fillion, G Damblin, A Petruzzi, R Mendizabal, ... Nuclear Science and Engineering 194 (8-9), 721-736, 2020 | 30 | 2020 |
| Quantification of the uncertainty of the physical models in the system thermal-hydraulic codes–PREMIUM benchmark T Skorek, A de Crécy, A Kovtonyuk, A Petruzzi, R Mendizábal, ... Nuclear Engineering and Design 354, 110199, 2019 | 28 | 2019 |
| Development of a pragmatic approach to model input uncertainty quantification for BEPU applications J Zhang, A Dethioux, A Kovtonyuk, C Schneidesch Nuclear Technology 205 (1-2), 140-152, 2019 | 21 | 2019 |
| Uncertainty and sensitivity analysis in reactivity-initiated accident fuel modeling: synthesis of organisation for economic co-operation and development (OECD)/nuclear energy … O Marchand, J Zhang, M Cherubini Nuclear Engineering and Technology 50 (2), 280-291, 2018 | 21* | 2018 |
| PREMIUM, a benchmark on the quantification of the uncertainty of the physical models in the system thermal-hydraulic codes: methodologies and data review F Reventós, A de Alfonso, J Zhang, A Kovtonyuk, A Dethioux, M Janssens, ... OECD, 2016 | 20 | 2016 |
| Nuclear fuel safety criteria technical review W Beck, P Blanpain, T Fuketa, A Gorzel, Z Hozer, K Kamimura, YH Koo, ... | 18 | 2012 |
| SAPIUM a systematic approach for input uncertainty quantification J Baccou, D Bestion, M Couplet, G Damblin, P Fillion, F Fouet, B Iooss, ... BEPU-2018, 2018 | 15 | 2018 |
| Towards a graded application of best estimate plus uncertainty methodology for non-LOCA transient analysis J Zhang, A Kovtonyuk, C Schneidesch Nuclear Engineering and Design 354, 110189, 2019 | 14 | 2019 |
| FUMAC: IAEA’s coordinated research project on fuel modelling in accident conditions M Veshchunov, J Stuckert, P Van Uffelen, W Wiesenack, J Zhang Trans. TopFuel, 2018 | 13 | 2018 |
| OECD/NEA benchmark on pellet-clad mechanical interaction modelling with fuel performance codes G Rossiter, S Massara, M Amaya Atomic Energy of Canada Limited, 2016 | 13 | 2016 |
| The role of verification & validation process in best estimate plus uncertainty methodology development J Zhang Nuclear Engineering and Design 355, 110312, 2019 | 12 | 2019 |
| Towards a systematic approach to input uncertainty quantification methodology J Baccou, J Zhang, E Nouy 17th International Topical Meeting on Nuclear Reactor Thermal Hydraulics …, 2017 | 12 | 2017 |
| Towards an industrial application of statistical uncertainty analysis methods to multi-physical modelling and safety analyses J Zhang, J Segurado, C Schneidesch | 12 | 2013 |
| Status update of the IAEA FUMAC project J Zhang, M Veshchunov Presented at the OECD/NEA Expert Group on Reactor Fuel Performance (EGRFP), 2016 | 8 | 2016 |
| Application of SAPIUM guidelines to Input Uncertainty Quantification: the ATRIUM project A Ghione, L Sargentini, G Damblin, P Fillion, J Baccou, R Sueur, B Iooss, ... 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics …, 2023 | 7 | 2023 |
| IAEA FUMAC Benchmark on the Halden, Studisvik and QUENCH-L1 LOCA tests D Pizzocri, A Bouloré, J Stuckert, P Van Uffelen, W Wiesenack, J Zhang Proceedings of the TopFuel 2018 Conference, 1-12, 2018 | 7 | 2018 |
| Coupled RELAP5/PANTHER/COBRA steam line break accident analysis in support of licensing DOEL 2 power uprate and steam generator replacement J Zhang, S Bosso, X Henno, K Ouliddren, CR Schneidesch, W Van Hove | 7 | 2004 |
| A commensurate industry approach to DEC A safety analysis M Havet, M Haedens, C Schneidesch, J Zhang Nuclear Engineering and Design 407, 112254, 2023 | 5 | 2023 |
Guillaume DamblinCEAAdresse e-mail validée de cea.fr
