ODS cladding fuel pins irradiation tests using the BOR-60 reactor |
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| Authors: | Takeji Kaito Yasuhide Yano Satoshi Ohtsuka Masaki Inoue Kenya Tanaka Alexander E. Fedoseev |
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| Affiliation: | 1. Japan Atomic Energy Agency , 4002, Narita-cho, Oarai-machi, Ibaraki , Japan;2. Research Institute of Atomic Reactors , Joint Stock Company , 10, Dimitrovgrad, Ulyanovsk region , Russia |
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| Abstract: | In order to confirm the irradiation behavior of ODS steels and thus judge their applicability to fuel claddings, fuel pin irradiation tests using 9Cr and 12Cr-ODS claddings developed by JAEA were conducted to burn-up of 11.9 at% and neutron dose of 51 dpa in the BOR-60. Superior properties of the ODS claddings concerning FCCI, dimensional stability under irradiation and so on were confirmed and indicated good application prospects for high burn-up fuel. On the other hand, anomalous irradiation behaviors, fuel pin failure and the microstructure change containing coarse and irregular precipitates, occurred in a part of the fuel pin with 9Cr-ODS cladding. This paper describes evaluation of the obtained irradiation data and the investigation results into the cause of the anomalous irradiation behaviors. |
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| Keywords: | FBR cladding material ODS MOX fuel fuel pin irradiation FCCI BOR-60 |
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