Irradiation of Ion Exchange Resin by TRIGA-II Reactor

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Air-dry and wet cation exchange resins, Diaion SK#I1, were irradiated in the H-form, Li-form, Mn-form, Cd-form and Pb-form by the TRIGA-II reactor at 100 kW and air-dry anion exchange resins, Diaion SA#100, were irradiated in I-form and BO3-form. The exchange capacity losses of these resins were measured after irradiation and compared with those produced in the same resins by the 60Co γ-ray irradiation. Ferrous and cc erric dosimeters were employed to measure the absorbed doses. The exchange capacity losses of the H-form, Mn form and I-form resins by the reactor irradiation were in agreement with those obtained in the same form resins by the 60Co γ-ray irradiation. Their values of H-form, Mn-form and I-form resins by the reactor irradiation were 13.5, 10.8, 27.6% respectively at 3.3×108r. In the case of Cd form, Li-form and BO3-form resins attaching the elements which have large cross sections with thermal neutron or emit heavy charged particles at the moment of neutron capture, the damage of the resins by the reactor irradiation was larger than that obtained in the same form resins by the 60Coγ-ray irradiation. Their values of Cd-form, Li-form and BO3-form resins by the reactor irradiation were 18.0, 33.8, 43.8% respectively at 3.3×108r. Also the radiation damage of the resins immersed in water or 3N acetic acid solution was larger than that obtained in the air-dry resins by the reactor or the 60Co-γ-ray irradiation.
社団法人日本アイソトープ協会の論文

Irradiation of Ion Exchange Resin by TRIGA-II Reactor

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概要

社団法人日本アイソトープ協会 | 論文

スポンサーリンク

Irradiation of Ion Exchange Resin by TRIGA-II Reactor

スポンサーリンク

概要

社団法人 日本アイソトープ協会 | 論文

スポンサーリンク

社団法人日本アイソトープ協会 | 論文