Resources
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Annual Meeting Proceedings
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To be effective, a perimeter intrusion detection system must comprise both sensor and rapid assessment components. The use of closed…
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Annual Meeting Proceedings
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A versatile, nondestructive system for the measurement of uranium and plutonium concentrations in process solutions from the reprocessing…
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PATRAM Proceedings
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The TN 1300 is a large capacity transpon-/storage cask for LWR fuel. Its performance has been tested by heat transfer experiments with…
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Annual Meeting Proceedings
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The Laboratories Department at the Savannah River Plant (SRP) has installed a six-place density meter with an automatic sampling device.…
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PATRAM Proceedings
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Storage of spent fuel is a common problem for many nuclear power plant operators worldwide. A shortage of space will soon become a reality…
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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…
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PATRAM Proceedings
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The paper presents information on the design, analysis and fabrication of two casks (TN·BRP and TN-REG) for the transport and storage of…
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PATRAM Proceedings
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On the basis of the provisional specifications of residues generated by a reprocessing plant, a conceptual design was prepared of a large…
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Annual Meeting Proceedings
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Since its inception, the nuclear industry has been engaged in providing protection against an insider threat. Although insider protection…
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PATRAM Proceedings
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A large, essentially unyielding, target for nuclear transportation package testing has been developed at Sandia National Laboratories in…
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Annual Meeting Proceedings
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As part of the Consolidated Fuel Reprocessing Program of the Fuel Recycle Division at the Oak Ridge National Laboratory (OFNL) , an…
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Annual Meeting Proceedings
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A safeguards sealing system is being developed for containers used by BNFL for transporting spent nuclear fuel, and its subsequent storage…
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Annual Meeting Proceedings
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This paper describes a mobile robot system designed to function as part of an overall security system at a high security facility. The…
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PATRAM Proceedings
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In Japan, post-irradiation examination (PIE) of nuclear fuels is being carried out quite frequently and the number of chopped fuel rods…
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PATRAM Proceedings
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PNC has had experience in the development and use of transport containers for mixed oxide fuel (Pu02-U02), plutonium dioxide, plutonium…
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PATRAM Proceedings
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Two kinds of rubber-type neutron shields for transport/storage packagings have been developed. In Type I, silicone rubber is the base…
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PATRAM Proceedings
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The highly active liquid wastes (HAW) resulting from reprocessing are vitrified within steel canisters to allow safe handling, transport…
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PATRAM Proceedings
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The Super-Phenix I fast reactor, with an output of 1200 MW(e), began commercial operation in 1985. Because adequate reprocessing capacity…
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Annual Meeting Proceedings
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The Office of Civilian Radioactive Waste Management (OCRWM) has been charged with the transportation of commercial spent nuclear fuel from…
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PATRAM Proceedings
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Two full-scale packages designed to carry radioactive materials were drop tested at the Oak Ridge National Laboratory. The unique aspects…