Feasibility Study on an Upgraded Future Monju Core Concept with Extended Operation Cycle Length of One Year and Increased Fuel Burnup

Kinjo, Hidehito; Kageyama, T.; Kitano, Akihiro; Usami, Shin

doi:10.13182/nt09-a8962

Cited by 1 publication

(1 citation statement)

References 3 publications

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“…The power density of all irradiation cycles are assumed to be constant, and the flux level and the helium production rate from total fission reactions are determined only at the beginning of the first irradiation cycle. Together with the cross-sections for JOYO cell model, those calculated for the cell models based on the planned MONJU upgraded core [12], and on the FS Phase II study discussed in the previous section are also shown in Table 5. These cross-section sets are respectively used in the formula, and the effect of the cross-section set is confirmed on the evaluation by the present formula.…”

Section: Comparison With Irradiated Fuel Samplementioning

confidence: 99%

Simple formula to evaluate helium production amount in fast reactor MA-containing MOX fuel and its accuracy

Akie

Sato

Suzuki

et al. 2013

Journal of Nuclear Science and Technology

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A simple formula is developed for the evaluation of the helium production amount in fast reactor minor actinide (MA) containing uranium-plutonium mixed oxide (MOX) fuel. For the subroutine use in the existing fuel behavior analysis code, the formula is designed putting emphasis on simplicity and quickness rather than accuracy. The accuracy of the formula is confirmed by comparing with the detailed calculation with SWAT code, and also with the post irradiation examination (PIE) results of the fuel pin irradiated at the experimental fast reactor JOYO. As a result, it is found that the formula evaluates the helium production amount with the difference of less than about 10% from the detailed calculation and the PIE results, when the MA isotope content is less than 5 wt.%. Based on these results, the formula is installed in the fuel behavior analysis code for the simulation of helium behavior in fast reactor fuels.

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Section: Comparison With Irradiated Fuel Samplementioning

confidence: 99%