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Journal of Nuclear Science and Technology Volume 56, 2019 - Issue 6
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Article

Model updates and performance evaluations on fuel performance code FEMAXI-8 for light water reactor fuel analysis

Yutaka UdagawaNuclear Safety Research Center, Japan Atomic Energy Agency, Ibaraki, JapanCorrespondence[email protected]
ORCID Iconhttps://orcid.org/0000-0001-9267-7606
ORCID Icon &
Masaki AmayaNuclear Safety Research Center, Japan Atomic Energy Agency, Ibaraki, Japan
Pages 461-470 | Received 13 Dec 2018, Accepted 06 Mar 2019, Published online: 26 Mar 2019

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V. D’Ambrosi, J. Sercombe, S. Bejaoui, A. Chaieb, B. Baurens, R. Largenton, A. Ambard, B. Boer, G. Bonny, M. Ševeček, L. E. Herranz, F. Feria Marquez, K. Inagaki, H. Ohta, F. Boldt, J. Sappl, R. Armstrong, A. Mohamad, Y. Udagawa, C. Cozzo, J. Klouzal, M. Vitezslav, J. Corson & J. Peltonen. (2024) P2M Simulation Exercise on Past Fuel Melting Irradiation Experiments. Nuclear Technology 210:2, pages 189-215.
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Afiqa Mohamad & Yutaka Udagawa. (2024) Modeling of the P2M Past Fuel Melting Experiments with the FEMAXI-8 Code. Nuclear Technology 210:2, pages 245-260.
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Yudai Tasaki, Yutaka Udagawa & Masaki Amaya. (2022) Development of fission gas release model for MOX fuel pellets with treatment of heterogeneous microstructure. Journal of Nuclear Science and Technology 59:3, pages 382-394.
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Articles from other publishers (8)

Yoshinori Taniguchi, Takeshi Mihara, Kazuo Kakiuchi & Yutaka Udagawa. (2024) High-temperature rupture failure of high-burnup LWR-MOX fuel under a reactivity-initiated accident condition. Annals of Nuclear Energy 195, pages 110144.
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Jakub Lüley, Branislav Vrban, Štefan Čerba, Filip Osuský & Vladimír Nečas. (2022) Fuel Performance Modeling at High Burn-Up by FEMAXI-6 Code. Journal of Nuclear Engineering and Radiation Science 8:4.
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Yanan He, Yuhang Niu, Fengrui Xiang, Yingwei Wu, Jing Zhang, Guanghui Su, Wenxi Tian & Suizheng Qiu. (2022) Preliminary development of a multi-physics coupled fuel performance code for annular fuel analysis under normal conditions. Nuclear Engineering and Design 393, pages 111810.
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Kazuo Kakiuchi, Masaki Amaya & Yutaka Udagawa. (2022) Irradiation growth behavior and effect of hydrogen absorption of Zr-based cladding alloys for PWR. Annals of Nuclear Energy 171, pages 109004.
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A. Magni, T. Barani, A. Del Nevo, D. Pizzocri, D. Staicu, P. Van Uffelen & L. Luzzi. (2020) Modelling and assessment of thermal conductivity and melting behaviour of MOX fuel for fast reactor applications. Journal of Nuclear Materials 541, pages 152410.
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Yutaka Udagawa, Takeshi Mihara, Yoshinori Taniguchi, Kazuo Kakiuchi & Masaki Amaya. (2020) The effect of base irradiation on failure behaviors of UO2 and chromia-alumina additive fuels under simulated reactivity-initiated accidents: A comparative analysis with FEMAXI-8. Annals of Nuclear Energy 139, pages 107268.
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Yoshinori Taniguchi, Yutaka Udagawa & Masaki Amaya. (2020) Analytical study of SPERT-CDC test 859 using fuel performance codes FEMAXI-8 and RANNS. Annals of Nuclear Energy 139, pages 107188.
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Yutaka Udagawa. (2020) Development and release of fuel performance code FEMAXI-8燃料挙動解析コードFEMAXI-8の開発と公開. Journal of the Atomic Energy Society of Japan 62:10, pages 555-559.
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