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Type:PATRAM Proceedings
Author(s):Gerald M. Foster, D. Keith Morton, Paul McConnell
Abstract:
Current activities of the American Society of Mechanical Engineers (ASME), Section III Subgroup on Containment Systems for Spent Fuel and…
Type:PATRAM Proceedings
Author(s):Milind M. Divate, Kathleen M. Trauth, Yingkui Li
Abstract:
The risk associated with the transportation of nuclear materials can be impacted by many factors of the transportation system, as well as…
Type:PATRAM Proceedings
Author(s):Chi-Fung Tso, John Harvey, Gary Jordan, Conrad Izatt, Robert Livesey
Abstract:
The United Kingdom Atomic Energy Authority (UKAEA) was formed in 1954 when the British Government set up a new body to oversee the nation's…
Type:PATRAM Proceedings
Author(s):Michel HARTENSTEIN
Abstract:
Denial and delay in transport of radioactive material, only because it is radioactive, is not uncommon; but more cases have been reported…
Type:PATRAM Proceedings
Author(s):Ana Célia F. Sobreira, Denise Bemelmans
Abstract:
REM Indústria e Comércio is a Brazilian private company which has been performing transport of radioactive material in Brazil for more than…
Type:PATRAM Proceedings
Author(s):Junichi Kishimoto, Akio Kitada, Chihiro Nishizak, Yuichi Saito
Abstract:
A series of drop tests with a full scale drop test model and a 1/2.5 scale drop test model for “MSF cask (Mitsubishi Spent Fuel Cask)” were…
Type:PATRAM Proceedings
Author(s):Gordon S. Bjorkman, Jr., Jason M. Piotter
Abstract:
In many spent fuel dry cask storage systems a welded steel canister provides the confinement boundary that prevents the release of…
Type:PATRAM Proceedings
Author(s):Danny A. Martinez
Abstract:
The OSR Project has developed a sealed source encapsulation to provide a method to assure US DOT special form containment of radioactive…
Type:PATRAM Proceedings
Author(s):Makoto Hirose, Toshiari Saegusa, Kenji Miyata, T. Nakatani, Hiroshi Akamatsu, Tomofumi YAMAMOTO
Abstract:
The Japan Society of Mechanical Engineers (JSME) established the Rules on Transport/Storage Packagings for Spent Fuel as a part of Codes…
Type:PATRAM Proceedings
Author(s):NULL NULL
Abstract:
Radioactive Material during transit requires additional physical security measures to ensure public safety at all times. Every year…
Type:PATRAM Proceedings
Author(s):Takaharu Maeguchi, Yoshiharu KAMIWAKI, Daiichi Ishiko, Tomofumi YAMAMOTO
Abstract:
Long-term reliability of basket material N-673 for transport and storage cask has been evaluated, taking effect of temperature and…
Type:PATRAM Proceedings
Author(s):Paul S. Blanton, Terry Wickland, Heather Klebba
Abstract:
This paper provides a brief history of the U.S. Type B 6M specification container, its introduction into U.S. Code of federal regulations…
Type:PATRAM Proceedings
Author(s):Jeffrey G. Arbital, Paul T. Mann
Abstract:
The Department of Energy (DOE) has been shipping university reactor fuels and other fissile materials in the 110-gallon Department of…
Type:PATRAM Proceedings
Author(s):Michael Tyacke, Frantisek Svitak, Jiri Rychecky, Miroslav Picek, Alexey Smirnov, Surgey Komarov, E. Bradley, Alexander Dudchenko, Konstantin Golubkin
Abstract:
The United States, the Russian Federation, and the International Atomic Energy Agency (IAEA) have been working together on a program called…
Type:PATRAM Proceedings
Author(s):Charles J. Temus, Alec Ross
Abstract:
A new package for the transport and storage of CANDU® reactor fuel includes the use of stackable fuel bundle support trays made from…
Type:PATRAM Proceedings
Author(s):Charles J. Temus, R. Montgomery
Abstract:
A Type B fresh fuel package has been developed to ship two PWR fuel assemblies. The package maximizes the number of fuel assemblies that…
Type:PATRAM Proceedings
Author(s):Jun Shimojo, Hiroshi Akamatsu, Hiroaki Taniuchi, Da YOKOE
Abstract:
Enriched borated aluminum alloys suitable for application to baskets in transport and storage casks for high burn-up spent fuels have been…
Type:PATRAM Proceedings
Author(s):Iain Gray, Bill Sievwright
Abstract:
As part of the process in the UK to assess the suitability of proposals for the packaging of intermediate level radioactive waste (ILW) for…
Type:PATRAM Proceedings
Author(s):M. Matsumoto, Naoteru Odano, Seiki OHNISHI, Makoto Morishima, M. Ohmura
Abstract:
The transport cask shielding analysis in Japan is carried out using the 2-dimensional Sn transport calculation code DOT2) and cross section…
Type:PATRAM Proceedings
Author(s):Daiichi Ishiko, Takeshi Ichihashi, Kouichi Tanimoto, Hironori Noguchi
Abstract:
To improve heat dissipation performance for the transport and storage cask, applicability of short and compact external fins (micro fins)…