Resources
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Type:Annual Meeting Proceedings
Abstract:
From stereophonic, positional sound to high-definition imagery that is crisp and clean, high fidelity computer graphics enhance our view,…
Type:Annual Meeting Proceedings
Abstract:
Large facilities handling sensitive materials in the nuclear fuel cycle are usually equipped with complex safeguards equipment which…
Type:Annual Meeting Proceedings
Abstract:
The Reflective Particle Tag (RPT) was developed during the late 20th century for identifying items accountable under bilateral nuclear…
Type:Annual Meeting Proceedings
Abstract:
The use of radiation imaging techniques to provide increased confidence in a dismantlement verification regime is still under…
Type:Annual Meeting Proceedings
Abstract:
Designing a measurement system that might be used in a nuclear facility is a challenging, if not daunting, proposition. The situation is…
Type:Annual Meeting Proceedings
Abstract:
Any verification measurement performed on potentially classified nuclear material must satisfy two seemingly contradictory constraints.…
Type:Annual Meeting Proceedings
Abstract:
An attribute measurement system (AMS) measures a number of unclassified attributes of potentially classified material. By only displaying…
Type:Annual Meeting Proceedings
Abstract:
Any verification measurement performed on potentially classified nuclear material must satisfy two constraints. First and foremost, no…
Type:PATRAM Proceedings
Abstract:
Included within Title 10 of the Code of Federal Regulations, Part 71 (10 CFR 71), are general licenses for fissile material shipments and…
Type:PATRAM Proceedings
Abstract:
Included within Title 10 of the Code of Federal Regulations, Part 71 (10 CFR 71), are general licenses for fissile material shipments and…
Type:Annual Meeting Proceedings
Abstract:
Basic study on remote analysis by combination of LIBS and AIRAS is performed to apply for a rapid and on-site analysis of low-…
Type:Annual Meeting Proceedings
Abstract:
There are many philosophies about nuclear fuel reprocessing with reference to safeguards and nuclear materials management. One camp…
Type:PATRAM Proceedings
Abstract:
IRSN is performing a study relative to the thermal behaviour of a new TN International package design for transport of spent fuel…
Type:PATRAM Proceedings
Abstract:
10 CFR 71 regulations [1] require that the containment boundary of a transport package is able to withstand a 30 ft (9 m) free drop unto a…
Type:PATRAM Proceedings
Abstract:
10 CFR 71 regulations [1] require that the containment boundary of a transport package is able to withstand a 30 ft (9 m) free drop unto a…
Type:Annual Meeting Proceedings
Abstract:
The UK National Nuclear Laboratory (NNL) has developed a methodology for objectively assessing reactor and fuel cycle systems for…
Type:Annual Meeting Proceedings
Abstract:
Dry casks are designed to confine spent nuclear fuel in sealed canisters and complex CFD models are used to analyze decay heat removal.…
Type:Annual Meeting Proceedings
Abstract:
Storage casks and transportation packages for spent nuclear fuel (SNF) are designed to confine SNF in sealed canisters or casks, provide…
Type:Annual Meeting Proceedings
Abstract:
Efficiency and reliability are two essential elements in implementing safeguards regimes. Remote monitoring (RM) is one alternative step…
Type:JNMM
Volume:39
Issue:1
Abstract:
The core mission of our profession is tominimize the risk of nuclear proliferationand its inevitable consequences. Accordingly,Tad Daley’s…