NDLI: TN™ 81: A Challenging Design

Content Provider	The American Society of Mechanical Engineers (ASME) Digital Collection
Author	Chanzy, Yves Otton, Camille
Copyright Year	2003
Abstract	With increasing burn-up, reprocessing of spent nuclear fuel yields higher quantities of radionuclides, with a powerful source term and high heat output. Improvement in the vitrification process and environmentally sound thinking have been drivers to reduce the number of transports of vitrified residues (High Level Waste) to interim storage facilities in their owner’s country: this results in higher concentrations of nuclides in the stable glass matrix. The challenge was to create, with almost the same allowable mass and dimensions, a transport/storage casks able to transport glass canisters with this new specifications. Improving the environmental performance of the glass canisters would be of no avail without the corresponding means of transport and storage. This is why COGEMA LOGISTICS introduced the TN™ 81 concept; a dual purpose cask able to handle the most demanding canisters from reprocessing: 56 kW instead of 41 kW, and to shield with efficiency greater gamma and neutron sources, which regulations have been made more stringent regarding the neutron quality factor. The paper will comment the choices made, the drop test campaigns run specifically, and report on the loading of the first TN 81 for KernKraftwerk Go¨sgen (KKG), Switzerland.
Sponsorship	Nuclear Engineering Division and Environmental Engineering Division
Starting Page	1231
Ending Page	1237
Page Count	7
File Format	PDF
ISBN	0791837327
DOI	10.1115/ICEM2003-4945
e-ISBN	0791837319
Volume Number	9th ASME International Conference on Radioactive Waste Management and Environmental Remediation: Volumes 1, 2, and 3
Conference Proceedings	ASME 2003 9th International Conference on Radioactive Waste Management and Environmental Remediation
Language	English
Publisher Date	2003-09-21
Publisher Place	Oxford, England
Access Restriction	Subscribed
Subject Keyword	Q-factor Regulations Neutron sources Vitrification Glass Neutrons Radioisotopes Spent nuclear fuels Dimensions Design Heat Storage Nuclides Logistics
Content Type	Text
Resource Type	Article

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