Resources
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Type:Annual Meeting Proceedings
Abstract:
The “Material Control and Surveillance for High Frequency Access Vaults” project sponsored by United States Department of Energy’s Office…
Type:Annual Meeting Proceedings
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The Rocky Flats Environmental Technology Site (RFETS) is now a Closure Site on an accelerated closure schedule. Closure not only involves…
Type:Annual Meeting Proceedings
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ABSTRACT This paper presents the validation of the Monte Carlo code MCNP-PoliMi for the simulation of nuclear safeguards experiments with…
Type:Annual Meeting Proceedings
Abstract:
Measurement of the fissile content of foreign-returned Material Test Reactor (MTR) spent fuel is one of the most important safeguards…
Type:Annual Meeting Proceedings
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This paper provides a brief overview of measures that have been taken in the Russian Federation to strengthen security of nuclear materials…
Type:Annual Meeting Proceedings
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A commercial, scintillator-based gamma-ray spectroscopic imaging system has measured the plutonium in-process inventory in a continuous-…
Type:Annual Meeting Proceedings
Abstract:
The Japan Nuclear Cycle Development Institute (JNC) has investigated a commercialized fast reactor cycle to make the maximum use of its…
Type:Annual Meeting Proceedings
Abstract:
In 2003, the U.S. Nuclear Regulatory Commission (NRC) requested that Los Alamos National Laboratory perform independent vulnerability…
Type:Annual Meeting Proceedings
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Maintaining continuity-of-knowledge (COK) is an important monitoring strategy for complementing safeguards measures based on nuclear…
Type:Annual Meeting Proceedings
Abstract:
A “cask weeping” incident occurs when a spent-fuel shipping cask that swiped “clean” for nonfixed contamination at the point of origin is…
Type:Annual Meeting Proceedings
Abstract:
The RT-1 plant at the PA Mayak complex of the Russian Federation is an operating nuclear reprocessing facility for civil spent fuel of VVER…
Type:Annual Meeting Proceedings
Abstract:
In previous studies the use of the Nuclear Materials Identification System (NMIS) for passive measurements on plutonium metal samples was…
Type:Annual Meeting Proceedings
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In this paper, the Monte Carlo code MCNP-PoliMi was used to investigate the possibility of conducting active measurements on highly…
Type:Annual Meeting Proceedings
Abstract:
Monte Carlo modelling studies of three different passive neutron-counting chambers: JCC51, JCC62 and FUNE are presented in this paper. The…
Type:Annual Meeting Proceedings
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Abstract For a number of years, the emphasis in materials control and accountability (MC&A) policy and analysis has been very heavily…
Type:Annual Meeting Proceedings
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MultiCal is a calorimeter control and data analysis software package widely used in the Department of Energy complex. A number of…
Type:Annual Meeting Proceedings
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In this era of strengthened safeguards measures, and especially following the recent introduction of high-resolution satellite imagery by…
Type:Annual Meeting Proceedings
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MyRIAM is the acronym for My Radioactivity In Air Monitor and points out that the device was designed for personal use to detect any…
Type:Annual Meeting Proceedings
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In this paper the neutron detector system (NDS) developed for the Californium-252 (252Cf) neutron source measurements of the fissile mass…
Type:Annual Meeting Proceedings
Abstract:
Development of an appropriate spent fuel verification methodology has been challenging for some time for a reactor that has a hard-to-…