KNK-II Knowledge Preservation Project: Component Oriented Classification

Component Category: -Fuel storage

3 documents found

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Conceptual study on the interim underwater storage of KNK-II fuel elements. Konzeptstudie zur Zwischenlagerung von KNK II-Brennelementen unter Wasser

Wasinger, K. (Kraftwerk Union A.G., Offenbach am Main (Germany, F.R.))
KFK--3278 - German - 1982

Abstract: For the intermediate storage of KNK II-fuel in water, Kraftwerk Union AG designed a 'wet storage facility for KNK II-fuel' by order of Kernforschungszentrum Karlsruhe. This wet storage facility is designed as At Reaktor (AR) storage by what the existing infrastructure of KNK II and KfK can be used. The storage of the fuel elements takes place in one storage pool equipped with compact storage racks. The maximum storage capacity is 10 cores of the KNK II. Cooling of the pool water is performed by a cooling system with natural recirculation which transfers the decay heat to the surrounding air. (orig.)

Key words: feasibility studies;knk-2 reactor;planning;spent fuel elements;spent fuel storage;storage;underwater
R&D Category: Decontamination, decommissioning, disassembly

display the document: 13696682.pdf


Conceptual design for interim storage of KNK II-fuel elements in a block storage facility. Konzeptstudie zur Zwischenlagerung von KNK II-Brennelementen in einem Blocklager

Arntzen, P.;Gasch, A. (Nuklear-Chemie und -Metallurgie G.m.b.H. (NUKEM), Hanau (Germany, F.R.))
KFK--3278 - German - 1982

Abstract: The storage facility is used for aircooled interim storage of irradiated KNK II-fuel elements from 10 reactor core-exchanges. The elements are canned before they are introduced into the storage facility. The heat produced by these elements is dissipated to the atmosphere via an indirect aircooling system. This cooling system is inherent safe and selfregulating. All codes, standards and regulations, relevant for design, are taken into consideration. The storage facility will be constructed on the KNK-site. The storage plant contains an extreme load influence from outside-safe storage part and a non extreme load influence from outside-safe reception and utility-part. (orig.)

Key words: feasibility studies;knk-2 reactor;planning;spent fuel elements;spent fuel storage
R&D Category: Decontamination, decommissioning, disassembly

display the document: 13696683.pdf


Concept on the interim storage of KNK-2 spent fuel elements in transport or storage containers. Konzept zur Zwischenlagerung bestrahlter KNK-II-Brennelemente in Transport-/Lagerbehaeltern

Bergmann, W.;Dries, G.;Laug, R. (Transnuklear G.m.b.H., Hanau (Germany, F.R.))
KFK--3278 - German - 1982

Abstract: The intented side for a container store is an area on the KfK premises. The immediate vicinity of the KNK II reactor was chosen in order to use the infrastructure, the physical protection and nuclear surveillance of that reactor. Delivery of the total of 315 fuel elements (= 10 core loads) for storage will occur biannually over a period of 20 years. It is proposed to load the containers with a mixture of 7 encapsulated fuel elements, of which a maximum of 2 will be test elements. The container is designed to prevent the release of radioactive materials and to guarantee subcriticality and the removal of decay heat in all possible incidents. The dose rate at the surface of the container is less than 20 mrem/h. Removal of the decay heat is assured by natural convection. The containers will be checked individually for leaktightness. A collective conduit keeps the KNK control room informed about the storage conditions. The storage buildings is divided into two main areas: the storage area, containing the 45 transport and storage containers positioned vertically by means of a 400 kN gantry crane, and the container reception area, containing the lorry entrance, the maintenance room, the measuring laboratory, and an installation room. The storage area is a control area, and the container reception area a surveillance area. (orig./HP)

Key words: containers;knk-2 reactor;spent fuel storage;transport
R&D Category: Decontamination, decommissioning, disassembly

display the document: 13696684.pdf