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

Available format(s)

Hardcopy , PDF

Language(s)

German

Published date

01-02-2014

Publisher

This document shall be used for calculating the decay power of uranium-plutonium mixed-oxide nuclear fuel in pressurized water reactors (PWRs).

DocumentType	Standard
Pages	45
ProductNote	THIS STANDARD ALSO REFERS TO :OREST-96
PublisherName	German Institute for Standardisation (Deutsches Institut für Normung)
Status	Current

KTA 3303 : 2015(R2017)	HEAT REMOVAL SYSTEMS FOR FUEL ASSEMBLY STORAGE POOLS IN NUCLEAR POWER PLANTS WITH LIGHT WATER REACTORS
KTA 3301 : 2015(R2017)	RESIDUAL HEAT REMOVAL SYSTEMS OF LIGHT WATER REACTORS
KTA 3413 : 2016(2017)	DETERMINATION OF LOADS FOR THE DESIGN OF A FULL PRESSURE CONTAINMENT VESSEL AGAINST PLANT-INTERNAL INCIDENTS

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DIN 25463-2:2014-02