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17.85 EUR
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53.55 EUR
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178.50 EUR
BS EN ISO 16793:2021
Nuclear fuel technology. Guidelines for ceramographic preparation of UO2 sintered pellets for microstructure examination
Nuclear fuel technology. Guidelines for ceramographic preparation of UO2 sintered pellets for microstructure examination
Released: 2021-02-22
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17.85 EUR
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53.55 EUR
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178.50 EUR
BS EN ISO 18256-1:2021
Nuclear fuel technology. Dissolution of plutonium dioxide-containing materials Dissolution of plutonium dioxide powders
Nuclear fuel technology. Dissolution of plutonium dioxide-containing materials Dissolution of plutonium dioxide powders
Released: 2021-02-23
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BS EN ISO 18256-2:2021
Nuclear fuel technology. Dissolution of plutonium dioxide-containing materials Dissolution of MOX pellets and powders
Nuclear fuel technology. Dissolution of plutonium dioxide-containing materials Dissolution of MOX pellets and powders
Released: 2021-02-22
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BS EN ISO 18557:2020
Characterisation principles for soils, buildings and infrastructures contaminated by radionuclides for remediation purposes
Characterisation principles for soils, buildings and infrastructures contaminated by radionuclides for remediation purposes
Released: 2020-05-07
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BS EN ISO 19017:2017
Guidance for gamma spectrometry measurement of radioactive waste
Guidance for gamma spectrometry measurement of radioactive waste
Released: 2018-01-18
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345.10 EUR
BS EN ISO 21483:2017
Determination of solubility in nitric acid of plutonium in unirradiated mixed oxide fuel pellets (U, Pu) O2
Determination of solubility in nitric acid of plutonium in unirradiated mixed oxide fuel pellets (U, Pu) O2
Released: 2018-01-18
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BS EN ISO 21484:2019
Nuclear Energy. Fuel technology. Determination of the O/M ratio in MOX pellets by the gravimetric method
Nuclear Energy. Fuel technology. Determination of the O/M ratio in MOX pellets by the gravimetric method
Released: 2019-06-21
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BS EN ISO 22765:2019
Nuclear fuel technology. Sintered (U,Pu)O<sub>2</sub> pellets. Guidance for ceramographic preparation for microstructure examination
Nuclear fuel technology. Sintered (U,Pu)O<sub>2</sub> pellets. Guidance for ceramographic preparation for microstructure examination
Released: 2019-06-21
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BS EN ISO 24459:2023
Determination of uranium content in samples coming from the nuclear fuel cycle by L-absorption edge spectrometry
Determination of uranium content in samples coming from the nuclear fuel cycle by L-absorption edge spectrometry
Released: 2023-08-21
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