Resources
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Type:Annual Meeting Proceedings
Abstract:
Most existing public opinion research on nuclear policy is devoted to civilian issues such as risk perception and communication with very…
Type:Annual Meeting Proceedings
Abstract:
More than five years have passed since the Integrated Support Center for Nuclear Nonproliferation and Nuclear Security (ISCN) was…
Type:Annual Meeting Proceedings
Abstract:
Final geological disposal of spent nuclear fuel is scheduled to start in Finland in 2023. To ascertain that necessary technical safeguards…
Type:Annual Meeting Proceedings
Abstract:
On 1 February 2016, Greenland and Denmark announced the details of a joint deal on uranium, along with two joint declarations on safeguards…
Type:Annual Meeting Proceedings
Abstract:
After the Fukushima Dai-ichi nuclear power plant accident, the Nuclear Regulatory Commission (NRA) investigated the Rokkasho reprocessing…
Type:Annual Meeting Proceedings
Abstract:
This work expands our understanding of uncertainty treatment for a class of nuclear safeguards measurement techniques. The focus of the…
Type:Annual Meeting Proceedings
Abstract:
To investigate the impact of interfacial bonding efficiency at pellet-pellet and pellet-clad interfaces of high-burnup (HBU) spent nuclear…
Type:Annual Meeting Proceedings
Abstract:
The nuclear nonproliferation regime has many robust measures in place to prevent the acquisition of a nuclear weapon, a key pillar of which…
Type:Annual Meeting Proceedings
Abstract:
Within its State Level Concept (SLC), the International Atomic Energy Agency (IAEA) envisions a State Level Approach (SLA) that considers,…
Type:PATRAM Proceedings
Abstract:
The transport of uranium hexafluoride (UF6) is carried out in large steel cylinders. During filling and extraction operations, some air in-…
Type:PATRAM Proceedings
Abstract:
The reference solution for the long-term management of intermediate and high level long-lived radioactive waste in France is defined in the…
Type:PATRAM Proceedings
Abstract:
All Member States with nuclear power programs or research reactors possess nuclear material and virtually all Member States possess and use…
Type:Annual Meeting Proceedings
Abstract:
In this work, we attempt to identify the isotopic composition of two plutonium-beryllium samples at the Indian Institute of Technology –…
Type:Annual Meeting Proceedings
Abstract:
Muon radiography was used to image the inside of a partially loaded Westinghouse MC-10 dry cask containing spent nuclear fuel at Idaho…
Type:PATRAM Proceedings
Abstract:
BAM is the German Federal Institute for Materials Research and Testing and the competent authority for mechanical and thermal safety…
Type:PATRAM Proceedings
Abstract:
It is common to determine the suitability of drop test II as defined by the IAEA Specific Safety Requirements No.SSR-6 paragraph 727 for…
Type:PATRAM Proceedings
Abstract:
IAEA security implementing guides, “Security in the Transport of Radioactive Material”, was published as NSS No.9 in 2008, and it is…
Type:PATRAM Proceedings
Abstract:
Currently the only option for USA utilities for Used Nuclear Fuel (UNF) management is wetstorage in the fuel pools and/or dry storage of…
Type:PATRAM Proceedings
Abstract:
In the current IAEA regulation for the safe transport of radioactive material [1] and all previous editions of this regulation, the fissile…
Type:PATRAM Proceedings
Abstract:
This paper discusses the effect of reactor operating parameters used in fuel depletion calculations on spent fuel cask reactivity, with…