Resources
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Type:PATRAM Proceedings
Abstract:
The paper presents a survey of available data on shock-absorbing materials in order to collect information for possible later adaptation of…
Type:PATRAM Proceedings
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BENCHMARKING THE Q/TRAN THERMAL ANALYSIS COMPUTER CODE. Q/TRAN, a new thermal analysis computer code, was examined for its use in modelling…
Type:PATRAM Proceedings
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CASK PERFORMANCE AND INTERFACE SPECIFICATIONS FOR SHIPMENT OF US SPENT LIGHT WATER REACTOR FUEL. Preliminary cask physical performance…
Type:PATRAM Proceedings
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Because of the importance of gathering data on the transport of radioactive materials - according to IAEA recommendations - the technical…
Type:PATRAM Proceedings
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CONTAINMENT ANALYSIS OF TRUPACT-1. TRUPACT·I is a packaging which will be used to transport contact-handled transuranic (CH-TRU) wastes…
Type:PATRAM Proceedings
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The paper presents an overview of the regulations, practices and experiences, as well as the systems of surveillance, in the transportation…
Type:PATRAM Proceedings
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According to contracts concluded between Cog6ma and its utility customers, wastes produced at different stages of the reprocessing process…
Type:PATRAM Proceedings
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Japan has 48 nuclear power plants with total electric capacity of 40 694 MW, including those in operation, under consuuction and in…
Type:PATRAM Proceedings
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The paper discusses the Czechoslovak approach to the licensing and regulation of nuclear materials transport, especially the transport of…
Type:PATRAM Proceedings
Abstract:
The TN 1300 is a large capacity transpon-/storage cask for LWR fuel. Its performance has been tested by heat transfer experiments with…
Type:PATRAM Proceedings
Abstract:
Storage of spent fuel is a common problem for many nuclear power plant operators worldwide. A shortage of space will soon become a reality…
Type:PATRAM Proceedings
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DESIGN AND SCALE MODEL TESTING OF THE NuPac 125-B RAIL CASK. The NuPac 125-B package was developed for defuelling the damaged Three Mile…
Type:PATRAM Proceedings
Abstract:
The paper presents information on the design, analysis and fabrication of two casks (TN·BRP and TN-REG) for the transport and storage of…
Type:PATRAM Proceedings
Abstract:
On the basis of the provisional specifications of residues generated by a reprocessing plant, a conceptual design was prepared of a large…
Type:PATRAM Proceedings
Abstract:
A large, essentially unyielding, target for nuclear transportation package testing has been developed at Sandia National Laboratories in…
Type:PATRAM Proceedings
Abstract:
In Japan, post-irradiation examination (PIE) of nuclear fuels is being carried out quite frequently and the number of chopped fuel rods…
Type:PATRAM Proceedings
Abstract:
PNC has had experience in the development and use of transport containers for mixed oxide fuel (Pu02-U02), plutonium dioxide, plutonium…
Type:PATRAM Proceedings
Abstract:
Two kinds of rubber-type neutron shields for transport/storage packagings have been developed. In Type I, silicone rubber is the base…
Type:PATRAM Proceedings
Abstract:
The highly active liquid wastes (HAW) resulting from reprocessing are vitrified within steel canisters to allow safe handling, transport…
Type:PATRAM Proceedings
Abstract:
The Super-Phenix I fast reactor, with an output of 1200 MW(e), began commercial operation in 1985. Because adequate reprocessing capacity…