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[en] A process description and system flow sheets have been prepared to support the design/build package for the Shippingport Spent Fuel Canister drying and inerting process skid. A process flow diagram was prepared to show the general steps to dry and inert the Shippingport fuel loaded into SSFCs for transport and dry storage. Flow sheets have been prepared to show the flows and conditions for the various steps of the drying and inerting process. Calculations and data supporting the development of the flow sheets are included
[en] There are two types of drying process. One is vacuum drying. Vacuum drying process is used widely because drying system is very simple. The other is forced dehydration drying. It is based on drying of forced convection using circulating of very dried gas. In vacuum drying, residual water in canister could be indirectly figured out by pressure rise of vaporization. The exact amount of water could not be directly measured. To find out how much residual water is remained during drying process, analytical calculation of vacuum drying process was performed. The calculation program of vacuum drying was developed to analyze analytically vacuum drying process of transfer/storage canister or cask with spent nuclear fuel. The effect of residual water and temperature on vacuum drying was compared. As the temperature increased, required time for vacuum drying decreased due to faster evaporation of residual water.
[en] Technical Issues for the interim dry storage of N Reactor Spent Nuclear Fuel (SNF) are discussed. Characterization data from fuel, to support resolution of these issues, are reviewed and new results for the oxidation of fuel in a moist atmosphere and the drying of whole fuel elements are presented. Characterization of associated K basin sludge is also discussed in light of a newly adopted disposal pathway
[en] In order to maintain the integrity of spent nuclear fuel when spent nuclear fuel is stored in the dry storage system, water within the canister is drained, residual moisture in the canister and spent nuclear fuel must be removed, and spent nuclear fuel have to be stored in inert gas atmosphere. Drying equipment is required to remove the residual moisture remaining in the canister of the spent nuclear fuel storage system and spent nuclear fuel. In order to evaluate the amount of residual moisture remaining in the canister after drying the moisture present in the canister of the spent nuclear fuel storage system using the drying equipment, measurement system capable of measuring moisture content should be established.
[en] The purpose of drying and filling helium gas in the canister is to prevent corrosion and hydration of the spent nuclear fuels as well as corrosion of internal canister components during the dry transport and storage. The drying process takes a considerable amount of time to be completed. In this study, two types of drying process technologies were compared and analyzed. The forced helium drying system is more complicated than the vacuum drying system. However, the helium drying system has some advantages. The main advantage is the heat transfer efficiency in the canister. Another advantage is the shorter drying time relative to vacuum drying. Moreover, the amounts of residual water in the canister during the drying processes were estimated through theoretical analysis. The results of this study will be used as the basic design data in a helium drying system.
[en] The paper at hands discusses the development of an integrated method to predict the fuel rod behavior of LWR-fuel during extended dry storage scenarios. It is well known that degradation effects exist under certain circumstances and that a fuel rod integrity assessment for long-term storage, handling and transport must take these effects into account. It will be elaborated why a complete coverage of the whole lifetime of the fuel rod is necessary. This includes the fabrication, reactor operation, wet storage, drying process, and the dry storage itself. Regarding this approach, a discussion on open questions and challenges will be given.
[en] The concepts of spray drying process and pebble-bed fluidized drying process for ADU slurry is presented. And the effects of ADU powder and UO2 powder/pellet by these processes using the statistic results from series production are discussed. It is believed that these drying methods have no influence on structure and shape of ADU particle, and thereby no difference will be made to the properties of UO2 powder and pellet. Thus, spray drying process can really be replaced by pebble-bed fluidized drying process. (10 figs., 6 tabs.)
[en] The UK will shortly cease reprocessing spent advanced gas reactor (AGR) fuel in favour of direct disposal, however since a permanent geological disposal facility is not envisaged as being available until 2075 interim storage will be required. The initial intention is to continue wet storage but it is possible that this may not be viable for as long as is hoped. Dry storage is commonly used worldwide for the interim storage of zirconium clad spent nuclear fuel however AGR fuel is stainless steel (SS) clad and as such a new safety case will be required to ensure that fuel can be adequately and safely dried. A rig has been designed to allow a comparison of the two main drying techniques in use; vacuum drying and flowed gas drying. This paper looks primarily at the design and development of the rig. Some of the initial data is presented to indicate how the rig was developed as a result of early results and is followed by some of the later test data to illustrate the improvements made.
[en] This study models the internal fluid flow from the center to the edge of a rotary atomizer wheel, the flow out of the atomizer, including the film, rivulet and ligament formation, as well as the subsequent atomization process associated with the atomizer outflow using computational fluid dynamics with a volume of fluid approach. The model shows how fluid exits through the overflow and not through the bushing at high inlet fluxes and can reproduce experimental results of power consumption. Furthermore, the drop-size distribution at a given distance from the bushing exit is in good agreement with experimental results. (Author)