FEMAXI-III,a computer code for fuel rod performance analysis |
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Authors: | K Ito M Ichikawa T Okubo Y Iwano |
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Affiliation: | 1. Nippon Nuclear Fuel development Co. Ltd., 2163 Narita - Machi, Oarai - Machi, Higashi - Ibaraki - Gun, Ibaraki - Pref., Japan;2. Fuel Reliability Laboratory, Division of Reactor Safety, Japan Atomic Energy Research Institute, Tokai - Mura, Naka - Gun, Ibaraki-Pref., Japan;3. Faculty of Science and Technology, Sophia University, 7 Kioicho, Chiyoda-Ku, Tokyo, Japan |
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Abstract: | This paper presents a method of fuel rod thermal-mechanical performance analysis used in the FEMAXI-III code. The code incorporates the models describing thermal-mechanical processes such as pellet-cladding thermal expansion, pellet irradiation swelling, densification, relocation and fission gas release as they affect pellet-cladding gap thermal conductance. The code performs the thermal behavior analysis of a full-length fuel rod within the framework of one-dimensional multi-zone modeling. The mechanical effects including ridge deformation is rigorously analyzed by applying the axisymmetric finite element method. The finite element geometrical model is confined to a half-pellet-height region with the assumption that pellet-pellet interaction is symmetrical. The 8-node quadratic isoparametric ring elements are adopted for obtaining accurate finite element solutions. The Newton-Raphson iteration with an implicit algorithm is applied to perform the analysis of non-linear material behaviors accurately and stably. The pellet-cladding interaction mechanism is exactly treated using the nodal continuity conditions. The code is applicable to the thermal-mechanical analysis of water reactor fuel rods experiencing variable power histories. |
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