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Report No.
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Irradiation creep of modified 316 and 15Cr-20Ni base austenitic S.S. fuel pins (MFA-1, 2) irradiated in FFTF

not registered; not registered  ; Mizuta, Shunji 

Modified 316 and 15Cr-20Ni base austenitic stainless steels had been developed by Japan Nuclear Cycle Development lnstitute as the candidate materials for Monju and Demonstration fast breeder reactor. Previously, irradiation creep correlation of modified 316 and 15Cr-20Ni had been evaluated using pressurized tubes irradiated in FFTF/MOTA. 0n the other hand, for other austenitic S.S. developed abroad, it was reported that irradiation creep behavior of fuel pin could not be sufficiently described using results of pressurized tube experiments. ln this study, irradiation creep properties of modified 316 and 15Cr-20Ni fuel pins (MFA-I, 2) irradiated in FFTF were evaluated. And irradiation deformation of MFA-1, 2 fuel pins were estimated using the irradiation creep correlation based on MOTA data. The results are summarized as follows : (1)Irradiation creep compliance B$$_{0}$$ calculated from MFA-I, 2 data are 5.6$$sim$$ 15.0$$times$$10$$^{-6}$$ [($$times$$I0$$^{26}$$n/m$$^{2}$$, E>0.1Mev)$$^{-1}$$(MPa)$$^{-1}$$], Which are larger than B$$_{0}$$ based on MOTA data of 2.2$$sim$$6.4$$times$$10$$^{-6}$$ and are within the range of B$$_{0}$$ of other austenitic S.S. abroad. (2)Creep-swelling coupling coefficient D derived from MFA-1, 2 data tend to decrease with increasing swelling rate. And the range of D based on MFA-1, 2 data include values calculated from MOTA data of 3.8$$sim$$8.2$$times$$10$$^{-3}$$ [(MPa)$$^{-1}$$] and for other austenitic S.S. abroad. (3)As the result that irradiation creep deformation of MFA-1, 2 fuel pins could be appropriately estimated using the irradiation creep correlation derived from MOTA data, it is considered that the creep, correlation based on MOTA data can be applied to estimation of fuel pin deformation.

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