A new burn-up module for application in fuel performance calculations targeting the helium production rate in (U,Pu)O2 for fast reactors

A. Cechet; S. Altieri; T. Barani; L. Cognini; S. Lorenzi; A. Magni; D. Pizzocri; L. Luzzi

doi:https://doi.org/10.1016/j.net.2020.12.001

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자료유형: 학술저널

저자정보: A. Cechet (Politecnico di Milano) S. Altieri (Politecnico di Milano) T. Barani (Politecnico di Milano) L. Cognini (Politecnico di Milano) S. Lorenzi (Politecnico di Milano) A. Magni (Politecnico di Milano) D. Pizzocri (Politecnico di Milano) L. Luzzi (Politecnico di Milano)

저널정보: 한국원자력학회 Nuclear Engineering and Technology Nuclear Engineering and Technology 제53권 제6호

발행연도: 2021.6

수록면: 1,893 - 1,908 (16page)

DOI: https://doi.org/10.1016/j.net.2020.12.001

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In light of the importance of helium production in influencing the behaviour of fast reactor fuels, in thiswork we present a burn-up module with the objective to calculate the production of helium in both inpileand out-of-pile conditions tracking the evolution of 23 alpha-decaying actinides. This burn-upmodule relies on average microscopic cross-section look-up tables generated via SERPENT high-fidelitycalculations and involves the solution of the system of Bateman equations for the selected set of actinidenuclides. The results of the burn-up module are verified in terms of evolution of actinide and heliumconcentrations by comparing them with the high-fidelity ones from SERPENT, considering two representativetest cases of (U,Pu)O2 fuel in fast reactor conditions. In addition, a code-to-code comparison ismade with the independent state-of-the-art module TUBRNP (implemented in the TRANSURANUS fuelperformance code) for the same test cases. The herein presented burn-up module is available in theSCIANTIX code, designed for coupling with fuel performance codes.

#Burn-up module #Oxide nuclear fuels #Fuel performance code #SCIANTIX #Helium production

참고문헌 (41)

참고문헌 신청

D.R. Olander / 1976 / Fundamental Aspects of Nuclear Reactor Fuel Elements, Technical Information Center e Energy Research and Development Administration

J. Rest / 2019 / Fission gas release from UO2 nuclear fuel : a review / J. Nucl. Mater 513:310~345

P. Van Uffelen / 2010 / Handb. Nucl. Eng :1519~1627

P. Van Uffelen / 2019 / A review of fuel performance modelling / J. Nucl. Mater 516:373~412

J. E. Kelly / 2014 / Generation IV International Forum : a decade of progress through international cooperation / Prog. Nucl. Energy 77:240~246

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