Application of the SCIANTIX fission gas behaviour module to the integral pin performance in sodium fast reactor irradiation conditions
The sodium-cooled fast reactor is among the innovative nuclear technologies selected in the framework of the development of Generation IV concepts, allowing the irradiation of uranium-plutonium mixed oxide fuels (MOX). A fundamental step for the safety assessment of MOX-fuelled pins for fast reactor...
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| Format: | Article |
| Language: | English |
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Elsevier
2022-07-01
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| Series: | Nuclear Engineering and Technology |
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| Online Access: | http://www.sciencedirect.com/science/article/pii/S1738573322000742 |
| _version_ | 1818536042685267968 |
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| author | A. Magni D. Pizzocri L. Luzzi M. Lainet B. Michel |
| author_facet | A. Magni D. Pizzocri L. Luzzi M. Lainet B. Michel |
| author_sort | A. Magni |
| collection | DOAJ |
| description | The sodium-cooled fast reactor is among the innovative nuclear technologies selected in the framework of the development of Generation IV concepts, allowing the irradiation of uranium-plutonium mixed oxide fuels (MOX). A fundamental step for the safety assessment of MOX-fuelled pins for fast reactor applications is the evaluation, by means of fuel performance codes, of the integral thermal-mechanical behaviour under irradiation, involving the fission gas behaviour and release in the fuel-cladding gap. This work is dedicated to the performance analysis of an inner-core fuel pin representative of the ASTRID sodium-cooled concept design, selected as case study for the benchmark between the GERMINAL and TRANSURANUS fuel performance codes. The focus is on fission gas-related mechanisms and integral outcomes as predicted by means of the SCIANTIX module (allowing the physics-based treatment of inert gas behaviour and release) coupled to both fuel performance codes. The benchmark activity involves the application of both GERMINAL and TRANSURANUS in their “pre-INSPYRE” versions, i.e., adopting the state-of-the-art recommended correlations available in the codes, compared with the “post-INSPYRE” code results, obtained by implementing novel models for MOX fuel properties and phenomena (SCIANTIX included) developed in the framework of the INSPYRE H2020 Project. The SCIANTIX modelling includes the consideration of burst releases of the fission gas stored at the grain boundaries occurring during power transients of shutdown and start-up, whose effect on a fast reactor fuel concept is analysed. A clear need to further extend and validate the SCIANTIX module for application to fast reactor MOX emerges from this work; nevertheless, the GERMINAL-TRANSURANUS benchmark on the ASTRID case study highlights the achieved code capabilities for fast reactor conditions and paves the way towards the proper application of fuel performance codes to safety evaluations on Generation IV reactor concepts. |
| first_indexed | 2024-12-11T18:32:53Z |
| format | Article |
| id | doaj.art-c9de49b260d34c189f9ef7d6460a145b |
| institution | Directory Open Access Journal |
| issn | 1738-5733 |
| language | English |
| last_indexed | 2024-12-11T18:32:53Z |
| publishDate | 2022-07-01 |
| publisher | Elsevier |
| record_format | Article |
| series | Nuclear Engineering and Technology |
| spelling | doaj.art-c9de49b260d34c189f9ef7d6460a145b2022-12-22T00:54:52ZengElsevierNuclear Engineering and Technology1738-57332022-07-0154723952407Application of the SCIANTIX fission gas behaviour module to the integral pin performance in sodium fast reactor irradiation conditionsA. Magni0D. Pizzocri1L. Luzzi2M. Lainet3B. Michel4Politecnico di Milano, Department of Energy, Nuclear Engineering Division, via La Masa 34, 20156, Milano, ItalyPolitecnico di Milano, Department of Energy, Nuclear Engineering Division, via La Masa 34, 20156, Milano, ItalyPolitecnico di Milano, Department of Energy, Nuclear Engineering Division, via La Masa 34, 20156, Milano, Italy; Corresponding author.Commissariat 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, FranceThe sodium-cooled fast reactor is among the innovative nuclear technologies selected in the framework of the development of Generation IV concepts, allowing the irradiation of uranium-plutonium mixed oxide fuels (MOX). A fundamental step for the safety assessment of MOX-fuelled pins for fast reactor applications is the evaluation, by means of fuel performance codes, of the integral thermal-mechanical behaviour under irradiation, involving the fission gas behaviour and release in the fuel-cladding gap. This work is dedicated to the performance analysis of an inner-core fuel pin representative of the ASTRID sodium-cooled concept design, selected as case study for the benchmark between the GERMINAL and TRANSURANUS fuel performance codes. The focus is on fission gas-related mechanisms and integral outcomes as predicted by means of the SCIANTIX module (allowing the physics-based treatment of inert gas behaviour and release) coupled to both fuel performance codes. The benchmark activity involves the application of both GERMINAL and TRANSURANUS in their “pre-INSPYRE” versions, i.e., adopting the state-of-the-art recommended correlations available in the codes, compared with the “post-INSPYRE” code results, obtained by implementing novel models for MOX fuel properties and phenomena (SCIANTIX included) developed in the framework of the INSPYRE H2020 Project. The SCIANTIX modelling includes the consideration of burst releases of the fission gas stored at the grain boundaries occurring during power transients of shutdown and start-up, whose effect on a fast reactor fuel concept is analysed. A clear need to further extend and validate the SCIANTIX module for application to fast reactor MOX emerges from this work; nevertheless, the GERMINAL-TRANSURANUS benchmark on the ASTRID case study highlights the achieved code capabilities for fast reactor conditions and paves the way towards the proper application of fuel performance codes to safety evaluations on Generation IV reactor concepts.http://www.sciencedirect.com/science/article/pii/S1738573322000742ASTRID case studyFuel pin performanceFission gas behaviourSCIANTIXGERMINALTRANSURANUS |
| spellingShingle | A. Magni D. Pizzocri L. Luzzi M. Lainet B. Michel Application of the SCIANTIX fission gas behaviour module to the integral pin performance in sodium fast reactor irradiation conditions Nuclear Engineering and Technology ASTRID case study Fuel pin performance Fission gas behaviour SCIANTIX GERMINAL TRANSURANUS |
| title | Application of the SCIANTIX fission gas behaviour module to the integral pin performance in sodium fast reactor irradiation conditions |
| title_full | Application of the SCIANTIX fission gas behaviour module to the integral pin performance in sodium fast reactor irradiation conditions |
| title_fullStr | Application of the SCIANTIX fission gas behaviour module to the integral pin performance in sodium fast reactor irradiation conditions |
| title_full_unstemmed | Application of the SCIANTIX fission gas behaviour module to the integral pin performance in sodium fast reactor irradiation conditions |
| title_short | Application of the SCIANTIX fission gas behaviour module to the integral pin performance in sodium fast reactor irradiation conditions |
| title_sort | application of the sciantix fission gas behaviour module to the integral pin performance in sodium fast reactor irradiation conditions |
| topic | ASTRID case study Fuel pin performance Fission gas behaviour SCIANTIX GERMINAL TRANSURANUS |
| url | http://www.sciencedirect.com/science/article/pii/S1738573322000742 |
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