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- W2020927133 abstract "An experimental study has been made of the distributions of plutonium and fission products across the wall thickness of some magnesium alloy cans after irradiation at ≈ 400 °C for 20–37 months in contact with uranium fuel. Some cans were experimental, of Magnox ZR55 (Mg/0.5 wt% Zr); some were standard, of Magnox AL80 (Mg/0.8 wt% Al). Plutonium was determined by methods involving controlled abrasion and alpha-counting; fission product activities were measured by photometry of contact autoradiographs. The ZR55 cans contained > 100 ppm Pu near the can inner surface and < 4 ppm Pu near the outer surface; plutonium had also segregated on the outer surface to the extent of 0.27 μg/cm2 in the sample examined. In the AL80 cans, irradiated at a similar temperature for twice the time, plutonium was confined to within 30–150 μm of the inner surface and over 60% of it was probably on the inner surface itself or in the oxide layer. Fission products had penetrated in substantial quantities to the outer surface of the ZR55 cans, with some segregation at the surface itself." @default.
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- W2020927133 date "1970-01-01" @default.
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- W2020927133 title "Plutonium and fission product distribution in some irradiated experimental magnox fuel element cans" @default.
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- W2020927133 doi "https://doi.org/10.1016/0022-3115(70)90003-6" @default.
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