Resources
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Type:PATRAM Proceedings
Abstract:
BNFL are developing a new package for the transport ofMOX fuels to European LWR utilities. This package is to comply with the 1996 edition…
Type:Annual Meeting Proceedings
Abstract:
All existing calorimeter systems for sensitive nuclear assay employ a heat bath surrounding the sample chamber. The purpose of the heat…
Type:PATRAM Proceedings
Abstract:
Large Nuclear Transport and Storage Flasks (50 Tonnes +)are constantly being developed in an attempt to optimise designs to suit the…
Type:Annual Meeting Proceedings
Abstract:
Originally, the international non-proliferation regime, including the IAEA safeguards, was formulated when the world was under the Cold-War…
Type:PATRAM Proceedings
Abstract:
Recent intercontinental radioactive material shipping campaigns have focused public and regulatory attention on the safety of transport of…
Type:Annual Meeting Proceedings
Abstract:
The Melox MOX fabrication plant is a modern, large-scale plant that features a high level of automation. For safeguards purposes Euratom is…
Type:PATRAM Proceedings
Abstract:
In 1991 and 1995, more than 310 spent fuel assemblies had been transported from Kori nuclear power plant #1, in which plant the storage…
Type:PATRAM Proceedings
Abstract:
fety of radioactive materials (RM) transportation is under strict control of the international norms of lAEA, aimed to ensure non-…
Type:PATRAM Proceedings
Abstract:
Considering the development of MOX fabrication and utilization in western continental Europe reactors, and in the framework ofMOX return to…
Type:PATRAM Proceedings
Abstract:
The reprocessing o f the spent fuel issued from the nuclear power plants allows to reuse most of the nuclear material for the manufacture…
Type:Annual Meeting Proceedings
Abstract:
Two computer programs are described: (1) the International Atomic Energy Agency (IAEA) Neutron Coincidence Counting (INCC) program and (2)…
Type:Annual Meeting Proceedings
Abstract:
It is the goal of remote monitoring to improve the effectiveness and efficiency of safeguards implementation. It is also expected that the…
Type:PATRAM Proceedings
Abstract:
The unique combination of the physical and mechanical properties of uranium made it possible to manufacture biological shield components of…
Type:PATRAM Proceedings
Abstract:
A new container concept called the MAXFORC® concept is presented which has been developed for transporting dangerous goods. For the first…
Type:PATRAM Proceedings
Abstract:
The paper describes the repacking act1vtt1es performed on a radioisotopes generator prototype, charged on 1976 with a Sr 90 source and…
Type:Annual Meeting Proceedings
Abstract:
The complete characterization of waste drums is a daunting task that challenges the most sophisticated non-intrusive techniques. It has…
Type:Annual Meeting Proceedings
Abstract:
An important future element of International Safeguards instrumentation is expected to be the merging of containment/surveillance and…
Type:PATRAM Proceedings
Abstract:
The R66 cask was designed and manufactured for CEA (French Atomic Energy Commission) by ROBATEL, using a new patented containment concept…
Type:Annual Meeting Proceedings
Abstract:
\"Programme 93+2\" was initiated in 1993 aiming at strengthening the effectiveness and improving the efficiency of the IAEA safeguards…
Type:PATRAM Proceedings
Abstract:
In accordance with the Record of Decision on a Nuclear Weapons Nonproliferation Policy Concerning Foreign Research Reactor Spent Nuclear…