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Neutron irradiation effects on $$^{11}$$B$$_{4}$$C and recovery by annealing

Donomae, Takako ; Tachi, Yoshiaki  ; Sekine, Manabu*; Morohashi, Yuko ; Akasaka, Naoaki; Onose, Shoji 

Use of moderator materials in Fast Breeder Reactor (FBR) is effective for transmutation technology, and $$^{11}$$B$$_{4}$$C is one of the candidates. Up to now, the behavior of $$^{10}$$B$$_{4}$$C as the Control rod material is well known, but that of $$^{11}$$B$$_{4}$$C is hardly investigated. In this paper, the radiation effects of $$^{11}$$B$$_{4}$$C pellets, neutron irradiated in the experimental fast reactor JOYO were studied. From the experimental results, it was observed that no macro-cracks were recognized in the irradiated $$^{11}$$B$$_{4}$$C pellets. But, bubble nucleation was found in grain and along grain boundaries of $$^{11}$$B$$_{4}$$C. And, it was shown that the conductivity of $$^{11}$$B$$_{4}$$C was higher than that of $$^{10}$$B$$_{4}$$C. During the annealing from room temperature to 1400$$^{circ}$$C, three recovery stages were found on thermal conductivity. It was suggested that, the recovery of B$$_{4}$$C was related to the dispersion behavior of helium. Judging from these results, as $$^{11}$$B$$_{4}$$C was mechanically more stable compared with $$^{10}$$B$$_{4}$$C under irradiation, it was shown that $$^{11}$$B$$_{4}$$C had high applicability for a moderator.

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Category:Materials Science, Ceramics

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