| Autor: |
L. Luzzi, T. Barani, B. Boer, A. Del Nevo, M. Lainet, S. Lemehov, A. Magni, V. Marelle, B. Michel, D. Pizzocri, A. Schubert, P. Van Uffelen, M. Bertolus |
| Jazyk: |
angličtina |
| Rok vydání: |
2023 |
| Předmět: |
|
| Zdroj: |
Nuclear Engineering and Technology, Vol 55, Iss 3, Pp 884-894 (2023) |
| Druh dokumentu: |
article |
| ISSN: |
1738-5733 |
| DOI: |
10.1016/j.net.2022.10.038 |
| Popis: |
Design and safety assessment of fuel pins for application in innovative Generation IV fast reactors calls for a dedicated nuclear fuel modelling and for the extension of the fuel performance code capabilities to the envisaged materials and irradiation conditions. In the INSPYRE Project, comprehensive and physics-based models for the thermal-mechanical properties of U–Pu mixed-oxide (MOX) fuels and for fission gas behaviour were developed and implemented in the European fuel performance codes GERMINAL, MACROS and TRANSURANUS. As a follow-up to the assessment of the reference code versions (“pre-INSPYRE”, NET 53 (2021) 3367–3378), this work presents the integral validation and benchmark of the code versions extended in INSPYRE (“post-INSPYRE”) against two pins from the SUPERFACT-1 fast reactor irradiation experiment. The post-INSPYRE simulation results are compared to the available integral and local data from post-irradiation examinations, and benchmarked on the evolution during irradiation of quantities of engineering interest (e.g., fuel central temperature, fission gas release). The comparison with the pre-INSPYRE results is reported to evaluate the impact of the novel models on the predicted pin performance. The outcome represents a step forward towards the description of fuel behaviour in fast reactor irradiation conditions, and allows the identification of the main remaining gaps. |
| Databáze: |
Directory of Open Access Journals |
| Externí odkaz: |
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