Energie- und Elektrotechnik

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  • Criticality safety in processing and handling of fissile materials - Principles

    Standard [CURRENT] 2024-12

    DIN 25403:2024-12

    Criticality safety in processing and handling of fissile materials - Principles

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  • Storage and keeping of other radioactive materials - Requirements on protection against radiation, fire and theft to be met by storage facilities and their installation rooms

    Standard [CURRENT] 2024-12

    DIN 25422:2024-12

    Storage and keeping of other radioactive materials - Requirements on protection against radiation, fire and theft to be met by storage facilities and their installation rooms

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  • Fuel assembly identification for nuclear power reactors

    Standard [CURRENT] 2016-10

    DIN 25433:2016-10

    Fuel assembly identification for nuclear power reactors

    This document applies to fuel assemblies of light water-cooled power reactors. It is also applicable to fuel assemblies or breeder assemblies of other types of power reactors, provided that the ...

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  • Calculation of the decay power in nuclear fuels of light water reactors - Part 1: Uranium oxide nuclear fuel for pressurized water reactors

    Standard [CURRENT] 2014-02

    DIN 25463-1:2014-02

    Calculation of the decay power in nuclear fuels of light water reactors - Part 1: Uranium oxide nuclear fuel for pressurized water reactors

    The decay power of nuclear fuels is the heat load generated after shutdown of a nuclear reactor by radioactive decay of the fission and activation products of the nuclear fuel. This document ...

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  • Calculation of the decay power in nuclear fuels of light water reactors - Part 2: Mixed-uranium-plutonium oxide (MOX) nuclear fuel for pressurized water reactors

    Standard [CURRENT] 2014-02

    DIN 25463-2:2014-02

    Calculation of the decay power in nuclear fuels of light water reactors - Part 2: Mixed-uranium-plutonium oxide (MOX) nuclear fuel for pressurized water reactors

    This document shall be applied for the calculation of the decay power of mixed uranium-plutonium oxide (MOX) nuclear fuel for pressurized water reactors. The user is provided with calculation ...

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  • Criticality safety for final disposal of nuclear fuels to be discarded

    Standard [CURRENT] 2012-08

    DIN 25472:2012-08

    Criticality safety for final disposal of nuclear fuels to be discarded

    This standard applies in the field of final disposal of nuclear fuels to be discarded for the operational phase and post operational phase of a final disposal site and shall be used for all ...

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  • Determination of density and open and closed porosity of uranium dioxide pellets; boiling water and immersion method

    Standard [CURRENT] 1991-04

    DIN 25494:1991-04

    Determination of density and open and closed porosity of uranium dioxide pellets; boiling water and immersion method

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    from 40.56 EUR VAT excluded

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  • Determination of the ²³²U isotopic content in uranium containing nuclear fuel solutions by α spectrometry

    Standard [CURRENT] 1996-06

    DIN 25711:1996-06

    Determination of the ²³²U isotopic content in uranium containing nuclear fuel solutions by α spectrometry

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    from 33.27 EUR VAT excluded

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  • Criticality safety taking into account the burnup of fuel for transport and storage of irradiated light water reactor fuel assemblies in casks

    Standard [CURRENT] 2015-04

    DIN 25712:2015-04

    Criticality safety taking into account the burnup of fuel for transport and storage of irradiated light water reactor fuel assemblies in casks

    This standard applies for the verification of criticality safety for transport and storage of irradiated fuel assemblies or other fuel rod arrangements (for example fuel rod cans or fuel rod ...

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    from 130.09 EUR VAT excluded

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  • Nuclear fuel technology - Determination of the isotopic and elemental uranium and plutonium concentrations of nuclear materials in nitric acid solutions by thermal-ionization mass spectrometry (ISO 8299:2019); English version EN ISO 8299:2021

    Standard [CURRENT] 2021-04

    DIN EN ISO 8299:2021-04

    Nuclear fuel technology - Determination of the isotopic and elemental uranium and plutonium concentrations of nuclear materials in nitric acid solutions by thermal-ionization mass spectrometry (ISO 8299:2019); English version EN ISO 8299:2021

    from 109.50 EUR VAT included

    from 102.34 EUR VAT excluded

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