Resources
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Type:Annual Meeting Proceedings
Abstract:
Funding Material, Control and Accountability (MC&A) system upgrades has been identified as a partial solution for mitigating the…
Type:Annual Meeting Proceedings
Abstract:
Recent policy from the Department of Energy/Office of Safeguards and Security (DOE/OSS) has identified the need to report nuclear materials…
Type:Annual Meeting Proceedings
Abstract:
The Japan Nuclear Cycle Development Institute (JNC) believes that the development of future nuclear fuel cycle technology should be…
Type:PATRAM Proceedings
Abstract:
Transport flasks are often filled with water as it provides both good cooling and shielding for irradiated fuel. However, during a fire,…
Type:PATRAM Proceedings
Abstract:
Following creation in the 1950s of the International Atomic Energy Agency (IAEA), the development of model regulations to provide for the…
Type:PATRAM Proceedings
Abstract:
Various analysis codes have been used for the 9m drop impact analysis of nuclear fuel casks, and analysis results are usually compared with…
Type:PATRAM Proceedings
Abstract:
Accidents could occur during the transportation of spent nuclear fuel and high-level radioactive waste. This paper describes the risks and…
Type:PATRAM Proceedings
Abstract:
Questions specific to the safety of rail transportation of spent nuclear fuel have been raised. The purpose of this paper is to examine the…
Type:PATRAM Proceedings
Abstract:
This paper decribes a methodical way to find critical drop angles or better a range of drop angles for oblique drops of a packages used for…
Type:PATRAM Proceedings
Abstract:
The shipment of non-irradiated BWR uranium fuel assemblies (including enriched reprocessed uranium or ERU) as well as BWR and PWR fuel rods…
Type:PATRAM Proceedings
Abstract:
The shipment of non-irradiated PWR uranium fuel assemblies (including enriched reprocessed uranium or ERU) from the fabrication facility to…
Type:PATRAM Proceedings
Abstract:
For the shipment of non-irradiated PWR mixed oxide (MOX) fuel assemblies from the fabrication facility to the power plant, the new ANF-18/…
Type:Annual Meeting Proceedings
Abstract:
This paper describes our progress towards the development of an autonomous tracking system capable of monitoring the movement of transport…
Type:PATRAM Proceedings
Abstract:
Dose equivalent rates at the premises of an interim storage facility have been evaluated by using the continuous energy Monte Carlo code…
Type:Annual Meeting Proceedings
Abstract:
The Russian Methodology and Training Center on Nuclear Material Control and Accountability (RMTC) in conjunction with Pacific Northwest…
Type:Annual Meeting Proceedings
Abstract:
In June 2000, the International Atomic Energy Agency (IAEA), in co-operation with the United States, organised a meeting of geophysical…
Type:PATRAM Proceedings
Abstract:
The UMS/MPC transport/storage system developed by NAC International consists of a multi-purpose canister that is called the Transportable…
Type:Annual Meeting Proceedings
Abstract:
Mercuric Iodide is a very promising material for the monitoring of stored materials that can be characterized by the energies and relative…
Type:Annual Meeting Proceedings
Abstract:
The unrecorded production of direct-use material constitutes a potential misuse of large thermal research reactors (with thermal power…
Type:Annual Meeting Proceedings
Abstract:
The United States and Russia have declared their mutual interest in dramatically reducing excess stocks of nuclear weapons and…