Resources
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Type:Annual Meeting Proceedings
Abstract:
The 252Cf shuffler assays fissile uranium and plutonium using active neutron interrogation and then counting the induced delayed neutrons.1…
Type:PATRAM Proceedings
Abstract:
According to the IAEA' 85 regulation para .543, when the temperature of a Type B package is evaluated under normal conditions of transport…
Type:Annual Meeting Proceedings
Abstract:
This paper describes a measurement of the precision of the new active-neutron-multiplicity assay technique, which is currently under…
Type:Annual Meeting Proceedings
Abstract:
At the Savannah River Site (SRS), large quantities of radioactive liquid waste are evaporated to reduce volume before eventual processing…
Type:Annual Meeting Proceedings
Abstract:
A system for measuring uranium concentration has been developed utilizing Rosemount pressure transmitters. The system originated with the…
Type:JNMM
Volume:20
Issue:3
Abstract:
Measurements of the nuclear radiation from spent reactor fuel are being considered to qualify assemblies for loading into casks that will…
Type:JNMM
Volume:20
Issue:4
Abstract:
There are to be target values established for Department of Energy (DOE) facilities which perform accountability measurements for nuclear…
Type:PATRAM Proceedings
Abstract:
A thorough understanding of the mechanical behavior of material in a specific cask is required to properly analyze the structural response…
Type:Annual Meeting Proceedings
Abstract:
The Department of Energy's (DOE) Office of Environmental Restoration and Waste Management (EM) faces major technical and institutional…
Type:JNMM
Volume:20
Issue:3
Abstract:
The PC program MEMO for determining the dispersion matrix (statistical measurement model) of a series of materials balance results is…
Type:Annual Meeting Proceedings
Abstract:
Department of Energy (DOE) Order 5630.13 calls for preparation and submission of site/facility specific Master Safeguards and Security…
Type:PATRAM Proceedings
Abstract:
A safety analysis has been conducted for the transports of non-heat-generating (low - to medium-level) radioactive waste to the planned…
Type:Annual Meeting Proceedings
Abstract:
The ASSESS Neutralization module (Neutralization) is part of the Analytic System and Software for Evaluating Safeguards and Security, (…
Type:PATRAM Proceedings
Abstract:
Transport regulations limit the release of activity from a radioactive materials package. A leakage test provides global information on the…
Type:Annual Meeting Proceedings
Abstract:
X and P control charts are used to monitor human error with Material Control and Accounting data at Nuclear Fuel Services, Inc. Charts use…
Type:Annual Meeting Proceedings
Abstract:
COG is a new point-wise Monte Carlo code being developed and tested at Lawrence Livermore National Laboratory (LLNL). It solves the…
Type:PATRAM Proceedings
Abstract:
The transport of dangerous goods in general and radioactive material in particular is an activity often undertaken by organizations…
Type:Annual Meeting Proceedings
Abstract:
The Analytic System and Software for Evaluating Safeguards and Security (ASSESS) is an integrated safeguards evaluation tool focusing on…
Type:PATRAM Proceedings
Abstract:
Engineers are challenged with a multitude of variables influencing their success in achieving optimum disposition of commercially generated…
Type:Annual Meeting Proceedings
Abstract:
The Analytic System and Software for Evaluation of Safeguards and Security (ASSESS) gathers site information in its Facility module,…