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Sim, Ki-Seob; Suk, Ho Chun; Tayal, M.
Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)1997
Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)1997
AbstractAbstract
[en] The possibility of the crevice corrosion in the CANDU-6 reactor pressure tube was evaluated for the case of using CANFLEX-NU 43-element bundles and compared with that for the case of using 37-element bundles. The results showed that the CANFLEX-nu fuel bundle is not likely to occur severe crevice corrosion. However, the potential for the crevice corrosion was found to exist. (author). 3 refs., 1 tab., 6 figs
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Aug 1997; 52 p
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