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Suzuki, Motoe; Nagase, Fumihisa
Proceedings of 2011 Water Reactor Fuel Performance Meeting (WRFPM 2011) (CD-ROM), 7 Pages, 2011/09
The behavior of MOX fuels which were base-irradiated in PWR and test-irradiated in the Halden reactor was analyzed by the latest version of fuel performance code FEMAXI-7. For the calculation conditions, linear heat rate history, power density profile, and coolant condition etc. were given consistently from the base- to test-irradiation to predict the fuel temperature, fission gas release rate, and cladding deformation, etc. Comparison of calculated values with the measured data during the test-irradiation shows a reasonable agreement in thermal analysis results such as fuel temperatures and fission gas release rates, while the cladding deformation, which is involved with various interactions, suggests that it is still necessary to analyze and consider an optimum combination of models and their parameters to obtain a satisfactory prediction.
Sugiyama, Tomoyuki; Udagawa, Yutaka; Suzuki, Motoe; Nagase, Fumihisa
Proceedings of 2011 Water Reactor Fuel Performance Meeting (WRFPM 2011) (CD-ROM), 6 Pages, 2011/09
The Japan Atomic Energy Agency has performed pulse irradiation tests using the NSRR to investigate fuel behavior under Reactivity-Initiated Accident (RIA) conditions. The NSRR tests have provided data of the pellet-cladding mechanical interaction (PCMI) failure of high burnup fuels up to 77 GWd/t. In particular, the PCMI failure limit is the important information which is needed in the reactor safety review. However, there are some differences between the NSRR tests and RIAs supposed in power reactors, such as the coolant temperature and the width of power pulse. Influence of these differences should be quantitatively evaluated in order to estimate the PCMI failure limit anticipated under the power reactor conditions from the NSRR data. This paper presents experimental results from a set of room and high temperature RIA tests, and discusses the evaluation procedure of the influence of coolant temperature and power pulse width on the failure limit on the basis of the experimental data.