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:PATRAM Proceedings
Abstract:
The A1 and A2 values described in the advisory material SSG-26 have been developed to provide the maximum allowable contents in packages…
Type:PATRAM Proceedings
Abstract:
This paper provides an overview of the thermal evaluation performed as part of the safety analysis validation of the P-48 overpack…
Type:PATRAM Proceedings
Abstract:
Notwithstanding the fact that solution reactors with liquid nuclear fuel are operated both in Russia and abroad, no handling procedures…
Type:PATRAM Proceedings
Abstract:
The Hi-flux Australian Reactor (HIFAR) operated from 1958 to 2007, at the Australian NuclearScience and Technology Organisation (ANSTO).…
Type:PATRAM Proceedings
Abstract:
People are exposed to low levels of radiation every day from many sources including natural radioactivity in soil, rocks, air, food and…
Type:PATRAM Proceedings
Abstract:
Flow characteristics inside a fuel basket containing a spent nuclear fuel assembly were analyzed. Since the geometry of a nuclear fuel…
Type:PATRAM Proceedings
Abstract:
In 2012, in the aftermath of the Fukushima accident, the IAEA reviewed transport of radioactive material activities. What emerged was that…
Type:PATRAM Proceedings
Abstract:
A sustainable Transportation Used Fuel program could be shortly defined as a not eventful program that you rarely hear about because it is…
Type:PATRAM Proceedings
Abstract:
Given the public nature of their operations, transporters of nuclear cargos have many responsibilities to discharge, not least the safety…
Type:PATRAM Proceedings
Abstract:
There is practically main regular supplier and operator in Russia, who supplies uranium material all over the world under international…
Type:PATRAM Proceedings
Abstract:
Tests of a surrogate pressurized water reactor fuel assembly have been conducted simulating normal conditions of truck and rail transport…
Type:PATRAM Proceedings
Abstract:
Storage of spent nuclear fuel and high-level waste in dual purpose casks (DPC) is related with the challenge of maintaining safety for…
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: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:
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…