Towards grain-scale modelling of the release of radioactive fission gas from oxide fuel. Part I: SCIANTIX

Zullo G.; Pizzocri D.; Magni A.; Van Uffelen P.; Schubert A.; Luzzi L.

doi:10.1016/j.net.2022.02.011

추천

검색

자료유형: 학술저널

저자정보: Zullo G. (Politecnico di Milano, Department of Energy, Nuclear Engineering Division) Pizzocri D. (Politecnico di Milano, Department of Energy, Nuclear Engineering Division) Magni A. (Politecnico di Milano, Department of Energy, Nuclear Engineering Division) Van Uffelen P. (European Commission, Joint Research Centre (JRC)) Schubert A. (European Commission, Joint Research Centre (JRC)) Luzzi L. (Politecnico di Milano, Department of Energy, Nuclear Engineering Division)

저널정보: 한국원자력학회 Nuclear Engineering and Technology Nuclear Engineering and Technology 제54권 제8호

발행연도: 2022.8

수록면: 2,771 - 2,782 (12page)

DOI: 10.1016/j.net.2022.02.011

이용수

📌

연구주제

📖

연구배경

🔬

연구방법

🏆

연구결과

초록· 키워드

오류제보하기

When assessing the radiological consequences of postulated accident scenarios, it is of primary interest to determine the amount of radioactive fission gas accumulated in the fuel rod free volume. The state-ofthe-art semi-empirical approach (ANS 5.4e2010) is reviewed and compared with a mechanistic approach to evaluate the release of radioactive fission gases. At the intra-granular level, the diffusiondecay equation is handled by a spectral diffusion algorithm. At the inter-granular level, a mechanistic description of the grain boundary is considered: bubble growth and coalescence are treated as interrelated phenomena, resulting in the grain-boundary venting as the onset for the release from the fuel pellets. The outcome is a kinetic description of the release of radioactive fission gases, of interest when assessing normal and off-normal conditions. We implement the model in SCIANTIX and reproduce the release of short-lived fission gases, during the CONTACT 1 experiments. The results show a satisfactory agreement with the measurement and with the state-of-the-art methodology, demonstrating the model soundness. A second work will follow, providing integral fuel rod analysis by coupling the code SCIANTIX with the thermo-mechanical code TRANSURANUS

#Oxide nuclear fuel #Fission gas behaviour #Radioactive release #ANS 5.4 #SCIANTIX

참고문헌 (0)

참고문헌 신청

참고문헌이 DBpia에서 서비스 중이라면, [참고문헌 신청]을 통해 등록해보세요

함께 읽어보면 좋을 논문

논문 유사도에 따라 DBpia 가 추천하는 논문입니다. 함께 보면 좋을 연관 논문을 확인해보세요!