Resources
Items marked as restricted are available to members only. Join INMM today to access over 60 years of insight from experts in the nuclear materials management industry.
Type:Annual Meeting Proceedings
Abstract:
Abstract Gas generation by plutonium-bearing materials in sealed contain- ers has been studied. The gas composition and pressure are…
Type:JNMM
Volume:38
Issue:3
Abstract:
Gas generation by plutonium-bearing materials in sealed containershas been studied. The gas composition and pressure are determinedover…
Type:JNMM
Volume:38
Issue:3
Abstract:
A series of tests was carried out to determine the threshold fordeflagration-to-detonation transition (DDT), structural loading,and…
Type:Annual Meeting Proceedings
Abstract:
Nuclear power is one of the main component of present and future energy supply mix. It can make a major contribution to meeting energy…
Type:Annual Meeting Proceedings
Abstract:
The Probabilistic Effectiveness Methodology (PEM) is a simulation that replicates threat motivation, capabilities, and intent, threat…
Type:PATRAM Proceedings
Abstract:
The Global Threat Reduction Initiative’s (GTRI) Off-Site Source Recovery Project (OSRP), which is administered by the Los Alamos National…
Type:PATRAM Proceedings
Abstract:
The Global Threat Reduction Initiative’s (GTRI) Off-Site Source Recovery Project (OSRP), which is administered by the Los Alamos National…
Type:Annual Meeting Proceedings
Abstract:
There is a recognized safeguards benefit from using process monitoring (PM) on nuclear facilities to complement nuclear materials…
Type:Annual Meeting Proceedings
Abstract:
The nuclear renaissance, the shortage of skilled talent, changing demographics, changing technologies and an uncertain economy has created…
Type:Annual Meeting Proceedings
Abstract:
A member state support program (MSSP) has been carried out to support the development of an IAEA safeguards approach on a pyroprocessing…
Type:Annual Meeting Proceedings
Abstract:
The direct, nondestructive measurement of fissile and fissionable isotopes in spent fuel is not yet possible. Current methods which infer…
Type:Annual Meeting Proceedings
Abstract:
Fission reactors emit large numbers of antineutrinos and this flux may be useful for the measurement of two quantities of interest for…
Type:Annual Meeting Proceedings
Abstract:
The Republic of Korea has been studying the nuclear fuel cycle options of direct disposal, DUPIC, and pyro-processing for the management…
Type:Annual Meeting Proceedings
Abstract:
Previous measurements of highly enriched uranium (HEU) storage castings performed by Oak Ridge National Laboratory (ORNL) at the Y-12…
Type:Annual Meeting Proceedings
Abstract:
The purpose of the proposed Fissile Material Cut-off Treaty (FMCT) is to ban production of fissile material for nuclear weapons and other…
Type:PATRAM Proceedings
Abstract:
The Task Group on Computational Modelling for Explicit Analyses in the ASME Boiler and Pressure Vessel Code committee was set up in August…
Type:PATRAM Proceedings
Abstract:
The Task Group on Computational Modelling for Explicit Analyses in the ASME Boiler and Pressure Vessel Code committee was set up in August…
Type:Annual Meeting Proceedings
Abstract:
The National Nuclear Security Administration’s Global Threat Reduction Initiative, facility operators, and local law enforcement agencies…
Type:PATRAM Proceedings
Abstract:
We must be transparent in our core activity which is an industrial field directly linked to electricity production. This activity is…
Type:PATRAM Proceedings
Abstract:
The Japan Atomic Energy Agency [JAEA] is planning to transport uranium and plutonium mixed oxide [MOX] powder for the prototype fast…