Assessment of INSPYRE-extended fuel performance codes against the SUPERFACT-1 fast reactor irradiation experiment

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, comprehensiv...

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Main Authors: 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
Format: Article
Language:English
Published: Elsevier 2023-03-01
Series:Nuclear Engineering and Technology
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Online Access:http://www.sciencedirect.com/science/article/pii/S1738573322005198
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author 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
author_facet 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
author_sort L. Luzzi
collection DOAJ
description 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.
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spelling doaj.art-c0d3eeb4aadc4293b00b625ebc4969572023-03-09T04:13:00ZengElsevierNuclear Engineering and Technology1738-57332023-03-01553884894Assessment of INSPYRE-extended fuel performance codes against the SUPERFACT-1 fast reactor irradiation experimentL. Luzzi0T. Barani1B. Boer2A. Del Nevo3M. Lainet4S. Lemehov5A. Magni6V. Marelle7B. Michel8D. Pizzocri9A. Schubert10P. Van Uffelen11M. Bertolus12Politecnico di Milano, Department of Energy, Nuclear Engineering Division, Via La Masa 34, 20156, Milano, Italy; Corresponding author.Politecnico di Milano, Department of Energy, Nuclear Engineering Division, Via La Masa 34, 20156, Milano, ItalyBelgian Nuclear Research Centre SCK·CEN, Boeretang 200, 2400, Mol, BelgiumENEA, FSN-ING-SIS, CR Brasimone, 40032, Camugnano (BO), ItalyCommissariat à l'Energie Atomique et aux Energies Alternatives, CEA DEC/SESC, 13108 St. Paul Lez Durance, FranceBelgian Nuclear Research Centre SCK·CEN, Boeretang 200, 2400, Mol, BelgiumPolitecnico di Milano, Department of Energy, Nuclear Engineering Division, Via La Masa 34, 20156, Milano, ItalyCommissariat à l'Energie Atomique et aux Energies Alternatives, CEA DEC/SESC, 13108 St. Paul Lez Durance, FranceCommissariat à l'Energie Atomique et aux Energies Alternatives, CEA DEC/SESC, 13108 St. Paul Lez Durance, FrancePolitecnico di Milano, Department of Energy, Nuclear Engineering Division, Via La Masa 34, 20156, Milano, ItalyEuropean Commission, Joint Research Centre, Directorate for Nuclear Safety and Security, P.O. Box 2340, 76125, Karlsruhe, GermanyEuropean Commission, Joint Research Centre, Directorate for Nuclear Safety and Security, P.O. Box 2340, 76125, Karlsruhe, GermanyCommissariat à l'Energie Atomique et aux Energies Alternatives, CEA DEC/SESC, 13108 St. Paul Lez Durance, FranceDesign 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.http://www.sciencedirect.com/science/article/pii/S1738573322005198MOX fuelSUPERFACT-1 irradiation experimentFuel performance codesGERMINALMACROSTRANSURANUS
spellingShingle 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
Assessment of INSPYRE-extended fuel performance codes against the SUPERFACT-1 fast reactor irradiation experiment
Nuclear Engineering and Technology
MOX fuel
SUPERFACT-1 irradiation experiment
Fuel performance codes
GERMINAL
MACROS
TRANSURANUS
title Assessment of INSPYRE-extended fuel performance codes against the SUPERFACT-1 fast reactor irradiation experiment
title_full Assessment of INSPYRE-extended fuel performance codes against the SUPERFACT-1 fast reactor irradiation experiment
title_fullStr Assessment of INSPYRE-extended fuel performance codes against the SUPERFACT-1 fast reactor irradiation experiment
title_full_unstemmed Assessment of INSPYRE-extended fuel performance codes against the SUPERFACT-1 fast reactor irradiation experiment
title_short Assessment of INSPYRE-extended fuel performance codes against the SUPERFACT-1 fast reactor irradiation experiment
title_sort assessment of inspyre extended fuel performance codes against the superfact 1 fast reactor irradiation experiment
topic MOX fuel
SUPERFACT-1 irradiation experiment
Fuel performance codes
GERMINAL
MACROS
TRANSURANUS
url http://www.sciencedirect.com/science/article/pii/S1738573322005198
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