No abstract available

[en] The invention discloses an inner container for a nuclear fuel transportation flask for irradiated fuel elements comprising a cylindrical shell having a dished end closure with a drainage sump and means for flushing out solid matter by way of the sump prior to removing a cover

[en] Decontamination of the internal surfaces of a 50-tonne Excellox type flask has been carried out at A.E.E. Winfrith by making the flask part of a circulating loop containing a solution of decontaminating reagent. Approximately 1.5 tonnes of reagent was circulated from a storage tank at flow rates up to 1000 litres per minute at a temperature of 80⁰C. A modified flask lid was designed and included a spacer which occupied the bulk of the internal volume of the flask. This spacer directed the flow and increased the linear velocity of the decontamination liquid across the flask surface. The main feed and return lines were brought through this lid with subsidiary pipework to drain and vent valves. Insulation of the flask and interconnecting pipework enabled the equipment and its circulating liquid content to be maintained at 80⁰C during the decontamination. Heating was achieved by means of electric immersion heaters in the reagent storage tank

No abstract available

[en] This document provides the structural analysis of the support frame for the Chem-Nuclear Systems (CNS) 1-13G Cask. The support frame will catch on underwater supports while the cask is being lowered into the pit, aiding in the removal of the cask lid in the load out chute in the K-Basins

[en] Heat dissipation, closure system, and internal arrangements are given for TN 12/1, TN 12/2, TN 13/2, and TN 17/2 cask models. These casks have the following advantages: a large payload, based upon the rail and maritime modes of transport and only limited by the crane capacities at operation sites; a high operational reliability, backed by the experience which has been gained for 15 years by Transnucleaire with casks of similar operational features; and the standardization of the small components and tools which results in common operation procedures for the different models and facilitates the procurement of spare parts. 6 figures, 1 table

[en] For criticality safety evaluation of the two spent fuel cask CASTOR RBMK-1500 and CONSTOR RBMK-1500 under normal conditions, SCALE 4.4a code system control module CSAS25 (KENO V.a) and MCNP 4C code were used. The conducted critical calculations for both cask types showed, that the values of the effective neutron multiplication factor k_eff obtained by both codes differ by 1 %. (author)

No abstract available

[en] A recent structural analysis of the T-3 Spent Fuel Containment Cask found problems with the design of the attachment system. Assumptions in the original SARP concerning the loading in the attachment bolts were found to be inaccurate in certain drop orientations. Similar weaknesses in the attachment system designs of other casks were also noted. This paper documents the lessons learned and their applicability to impact limiter attachment system designs

[en] The SNR 300 LMFBR prototype nuclear power plant (SNR 300), is ready to be loaded with fresh fuel assemblies. TRANSNUKLEAR GMBH Hanau (TNH) has designed a large capacity cask for 9 fuel assemblies. Two casks are built and will be shipped simultaneously by TNH's special security truck SIFA. The delivery of the fuel assemblies to the SNR 300 will take 12 shipments all together. The paper describes the package design