Energy, Electronic engineering, Electronics

Energy technology, Electronic engineering, Electronics

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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

This document applies to the handling of fissile materials within nuclear facilities. The core zone of nuclear reactors is excluded. Special requirements apply to the transport of fissile ...

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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 [PRE-ORDER] [PLEASE NOTE THE WARNING NOTICE] 2026-02

DIN 25422:2026-02

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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This document is being corrected. The corrected version can be pre-ordered and will be delivered as soon as the document is corrected. If you have already received this document, a corrected version will be automatically sent to you.

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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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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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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

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