Assessment of three European fuel performance codes against the SUPERFACT-1 fast reactor irradiation experiment

L. Luzzi; T. Barani; B. Boer; L. Cogni; A. Del Nevo; M. Lainet; S. Lemehov; A. Magni; V. Marelle; B. Michel; D. Pizzocri; A. Schubert; P. Van Uffelen; M. Bertolus

doi:https://doi.org/10.1016/j.net.2021.04.010

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저자정보: L. Luzzi (Politecnico di Milano) T. Barani (Politecnico di Milano) B. Boer (Studiecentrum voor Kernenergie (SCK·CEN), Boeretang 200, 2400 Mol, Belgium) L. Cogni (Politecnico di Milano) A. Del Nevo (ENEA, FSN-ING-SIS, CR Brasimone, 40032, Camugnano (BO), Italy) M. Lainet (Commissariat a l'Energie Atomique et aux Energies Alternatives, CEA DEC/SESC) S. Lemehov (Studiecentrum voor Kernenergie (SCK·CEN), Boeretang 200, 2400 Mol, Belgium) A. Magni (Politecnico di Milano) V. Marelle (Commissariat a l'Energie Atomique et aux Energies Alternatives, CEA DEC/SESC) B. Michel (Commissariat a l'Energie Atomique et aux Energies Alternatives, CEA DEC/SESC) D. Pizzocri (Politecnico di Milano) A. Schubert (European Commission, Joint Research Centre, Directorate for Nuclear Safety and Security) P. Van Uffelen (European Commission, Joint Research Centre, Directorate for Nuclear Safety and Security) M. Bertolus (Commissariat a l'Energie Atomique et aux Energies Alternatives, CEA DEC/SESC)

저널정보: 한국원자력학회 Nuclear Engineering and Technology Nuclear Engineering and Technology 제53권 제10호

발행연도: 2021.10

수록면: 3,367 - 3,378 (12page)

DOI: https://doi.org/10.1016/j.net.2021.04.010

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The design phase and safety assessment of Generation IV liquid metal-cooled fast reactors calls for theimprovement of fuel pin performance codes, in particular the enhancement of their predictive capabilities towards uranium-plutonium mixed oxide fuels and stainless-steel cladding under irradiation infast reactor environments. To this end, the current capabilities of fuel performance codes must be critically assessed against experimental data from available irradiation experiments. This work is devoted tothe assessment of three European fuel performance codes, namely GERMINAL, MACROS and TRANSURANUS, against the irradiation of two fuel pins selected from the SUPERFACT-1 experimental campaign. The pins are characterized by a low enrichment (~ 2 wt.%) of minor actinides (neptunium and americium)in the fuel, and by plutonium content and cladding material in line with design choices envisaged forliquid metal-cooled Generation IV reactor fuels. The predictions of the codes are compared to severalexperimental measurements, allowing the identification of the current code capabilities in predictingfuel restructuring, cladding deformation, redistribution of actinides and volatile fission products. Theintegral assessment against experimental data is complemented by a code-to-code benchmark focusedon the evolution of quantities of engineering interest over time. The benchmark analysis points out thedifferences in the code predictions of fuel central temperature, fuel-cladding gap width, cladding outerradius, pin internal pressure and fission gas release and suggests potential modelling development pathstowards an improved description of the fuel pin behaviour in fast reactor irradiation conditions.

#SUPERFACT-1 irradiation experiment #Fuel performance #GERMINAL #MACROS #TRANSURANUS #MOX fuel #Assessment and benchmark

참고문헌 (86)

참고문헌 신청

GIF (Generation IV International Forum) / 2018 / GIF R&D Outlook for Generation IV Nuclear Energy Systems - 2018 Update

GIF (Generation IV International Forum) / 2019 / Annual Report 2019

T. Beck / 2017 / Conceptual design of ASTRID fuel sub-assemblies / Nucl. Eng. Des 315:51~60

ESFR-SMART / ESFR-SMART European H2020 Project

G. Grasso / 2014 / The core design of ALFRED, a demonstrator for the European lead-cooled reactors / Nucl. Eng. Des 278:287~301

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