Resources
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Type:Annual Meeting Proceedings
Abstract:
The adaptation of a batch follow up technique to the production line of a commercial mixed oxide fuel assembly facility is described and…
Type:PATRAM Proceedings
Abstract:
Static and dynamic analyses of an impact limiter for a spent fuel cask have been performed using the finite element analysis code PRONT02D…
Type:PATRAM Proceedings
Abstract:
Hypothetical accident conditions for testing transport casks require the cask to withstand a 9-meter drop onto an unyielding target at a…
Type:PATRAM Proceedings
Abstract:
Spent fuel can be stored at a reactor site in accordance with 10 CFR 72. One method of storage is to use a cask to contain and shield the…
Type:JNMM
Volume:17
Issue:4
Abstract:
In 1967, a committee at Brookhaven National Laboratory suggested that the Atomic Energy Commission (AEC) should establish a safeguards…
Type:Annual Meeting Proceedings
Abstract:
Manpower is the most expensive single feature of a security system. In a climate of close scrutiny for government expenditures the…
Type:PATRAM Proceedings
Abstract:
As one of the most important producer of nuclear electricity in the world, EDF is concerned by all the aspects of the transport of nuclear…
Type:JNMM
Volume:18
Issue:1
Abstract:
The ability of this country to move forward into and have an impact on the nuclear technology of the 21st century will be dependent upon…
Type:PATRAM Proceedings
Abstract:
The overall weight of a spent-fuel transport cask is minimized when its gamma shield consists of depleted uranium only; however, because of…
Type:Annual Meeting Proceedings
Abstract:
The implementation of U. S. Department of Energy (DOE) Orders and Guides is a major responsibility for site personnel. With the issuance of…
Type:PATRAM Proceedings
Abstract:
Pacific Nuclear Transport Ltd (PNTL) a subsidiary of British Nuclear Fuels plc (BNFL) was established in 1975 to transport irradiated…
Type:Annual Meeting Proceedings
Abstract:
Due to the 1979 accident at Three Mile Island Unit 2 (TMI-2), fuel material was transported through the reactor coolant system (RCS). As…
Type:PATRAM Proceedings
Abstract:
A low-level radioactive-waste shipping vessel in which as auch as 3000 radwaste drums were loaded was supposed in the study, and the gamma-…
Type:Annual Meeting Proceedings
Abstract:
The Euratom Safeguards Directorate has over the past five years evaluated, field-tested, purchased, calibrated and introduced in to routine…
Type:Annual Meeting Proceedings
Abstract:
To assess facility security systems, you need powerfull tools to help you. It is the only way to have a systematic approach, to be able to…
Type:Annual Meeting Proceedings
Abstract:
For years the lighting industry has manually entered and manually performed calculations on the photometric data that is necessary for…
Type:Annual Meeting Proceedings
Abstract:
Near-Real Time Accountancy (NRTA) appears to be an adequate tool to achieve the IAEA's safeguarding criteria in future large scale plants.…
Type:Annual Meeting Proceedings
Abstract:
With the advent of automated photographic badge making systems and automated access control systems, the need for new badge making…
Type:PATRAM Proceedings
Abstract:
This study makes an inventory of external irradiatjon dose equivalents and collective dose equivalents received by workers and the public…
Type:Annual Meeting Proceedings
Abstract:
The Department of Energy (DOE) is investigating the possible use of ductile cast iron (DCI) as a candidate material for radioactive…