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Measurement of fission gas release rates from a uranium dioxide fuel pin during irradiation in a fast reactor

W.B. Bremner, A.B.G. Washington

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Abstract

An experiment carried out in the Dounreay fast reactor to measure continuously the fission gases released from a long uranium dioxide fuel pin irradiated to a burn-up of 2% is described. The gases were swept by a helium purge from the pin to the reactor top where they were analyzed by bottle sampling and in line gamma spectrometry. Measured release rates increased with isotopic half life from about 0.03% for /sup 89/Kr (half life 3.2 min) to 60% for stable gases. Although the release rates varied throughout the irradiation they did not increase significantly with rapid changes in reactor power. (auth)

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An experiment carried out in the Dounreay fast reactor to measure continuously the fission gases released from a long uranium dioxide fuel pin irradiated to a burn-up of 2% is described. The gases were swept by a helium purge from the pin to the reactor top where they were analyzed by bottle sampling and in line gamma spectrometry. Measured release rates increased with isotopic half life from about 0.03% for /sup 89/Kr (half life 3.2 min) to 60% for stable gases. Although the release rates varied throughout the irradiation they did not increase significantly with rapid changes in reactor power. (auth)

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Available abstract

An experiment carried out in the Dounreay fast reactor to measure continuously the fission gases released from a long uranium dioxide fuel pin irradiated to a burn-up of 2% is described. The gases were swept by a helium purge from the pin to the reactor top where they were analyzed by bottle sampling and in line gamma spectrometry. Measured release rates increased with isotopic half life from about 0.03% for /sup 89/Kr (half life 3.2 min) to 60% for stable gases. Although the release rates varied throughout the irradiation they did not increase significantly with rapid changes in reactor power. (auth)

Key concepts: Radiochemistry, Bottle, Irradiation, Fission products, Uranium dioxide, Fission, Uranium, Materials science

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