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:
The most time consuming process in uranium or plutonium isotopic analyses is performing the requisite chromatographic separation of the…
Type:Annual Meeting Proceedings
Abstract:
Inverse depletion/decay methods are useful in nuclear forensics. Previously, inverse methods were applied to the prediction of burnup,…
Type:PATRAM Proceedings
Abstract:
The KN-18 SNF (spent nuclear fuel) transport cask is a newly developed cask intended for the dry or wet transportation of up to 18 PWR…
Type:PATRAM Proceedings
Abstract:
The KN-18 SNF (spent nuclear fuel) transport cask is a newly developed cask intended for the dry or wet transportation of up to 18 PWR…
Type:Annual Meeting Proceedings
Abstract:
Cooperation among countries to improve the security of radioactive and nuclear assets is clearly the key to success in establishing a…
Type:Annual Meeting Proceedings
Abstract:
The main goals of Value Stream Analysis (VSA) are to improve quality, cost, and delivery of a product or service by eliminating waste.…
Type:Annual Meeting Proceedings
Abstract:
In 2007 former Secretaries of State, George Shultz and Henry Kissinger, former Secretary of Defense, William Perry, and former Senator Sam…
Type:Annual Meeting Proceedings
Abstract:
On April 5 2009 President Barak Obama declared that under his leadership the United States would “seek the security of a world free of…
VERIFICATION OF ACTIVITY RELEASE COMPLIANCE WITH REGULATORY LIMITS WITHIN SPENT FUEL TRANSPORT CASKS
Type:PATRAM Proceedings
Abstract:
Admissible limits for activity release from Type B packages for spent fuel transport specified in the IAEA regulations (10-6 A2 per hour…
Type:PATRAM Proceedings
Abstract:
Admissible limits for activity release from Type B packages for spent fuel transport specified in the IAEA regulations (10-6 A2 per hour…
Type:PATRAM Proceedings
Abstract:
The mechanical analyses in the context of the transport licensing of the type B(U)F package CASTOR® HAW28M Cask for Transport and Storage…
Type:PATRAM Proceedings
Abstract:
The Global Nuclear Fuel (GNF) RAJ-II fuel package for transportation of BWR fuel bundles is a second-generation, Type B(F), all stainless…
Type:PATRAM Proceedings
Abstract:
Development: • RAJ-II BWR fresh fuel transport package developed in Japan as replacement for first generation design. • Drop tested in…
Type:Annual Meeting Proceedings
Abstract:
Comprehensive disarmament means to put all fissile materials under international safeguards. Once a nuclear weapon free world has been…
Type:Annual Meeting Proceedings
Abstract:
We?present?the?recent?results?of?our?development?effort?with?liquid?scintillators?at? Lawrence?Livermore?National?Laboratory.?Historically…
Type:Annual Meeting Proceedings
Abstract:
The complexity of physical protection systems has increased to address modern threats to national security and emerging commercial…
Type:Annual Meeting Proceedings
Abstract:
The main objective of Virtual Reality – VR – is creating a computer-based experience normally by means of realistically…
Type:Annual Meeting Proceedings
Abstract:
Large Size Dried (LSD) spikes are currently used in many facilities in Japan (and around the world) for uranium and plutonium accountancy…
Type:PATRAM Proceedings
Abstract:
The paper presents technical details of the drop test performance as well as some experimental results of tests carried out with the…
Type:PATRAM Proceedings
Abstract:
The paper presents technical details of the drop test performance as well as some experimental results of tests carried out with the…