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 Cask Analysis Fire Environment (CAFE) computer code is designed to accurately predict convection and radiation heat transfer to a…
Type:PATRAM Proceedings
Abstract:
American and international standards relative to leakage tests on packages for shipment indicate that the leakage rates of the test…
Type:PATRAM Proceedings
Abstract:
Currently, criticality studies of Pressurized Water Reactor (PWR) Mixed OXide (MOX) (uranium and plutonium) fuel assemblies in transport…
Type:PATRAM Proceedings
Abstract:
Testing large type B packages is expensive and often limited by the availability of test facilities. As IAEA’s Regulations recommend, an…
Type:PATRAM Proceedings
Abstract:
The CONSTOR® is a steel-concrete-steel sandwich cask design. It was developed with special consideration to an economical and effective way…
Type:PATRAM Proceedings
Abstract:
Within the year 2000, TRANSNUCLEAIRE performed almost 3000 transports of nuclear and radioactive materials. This impressive international…
Type:PATRAM Proceedings
Abstract:
A Report on preliminary design of the Mixed Uranium-Plutonium Oxide (MOX) Fresh Fuel Package (MFFP). Packaging Technology, Inc. (PacTec) is…
Type:PATRAM Proceedings
Abstract:
BAM as German competent authority for mechanical and thermal safety assessment, and for the approval of quality assurance measures in…
Type:PATRAM Proceedings
Abstract:
In 1796 in Europe the first forms of dangerous goods transport (gunpowder) regulations were published. Radioactive material at that time…
Type:PATRAM Proceedings
Abstract:
Packaging and transportation systems used to transfer radioactive materials and wastes onsite (e.g., within Site boundaries where public…
Type:PATRAM Proceedings
Abstract:
ABSTRACT The objective of this paper is to demonstrate that casks (NFT type) transporting high burn-up spent fuel not only meet the…
Type:PATRAM Proceedings
Abstract:
If the natural Uranium hexafluoride (UF6) transport container is involved in a fire test condition as described in the new requirements…
Type:PATRAM Proceedings
Abstract:
Spent nuclear fuel from the Hanford N-Reactor is currently stored in pools, the K-East and K-West basins. As part of Hanford’s…
Type:PATRAM Proceedings
Abstract:
Oak Ridge National Laboratory (ORNL) has a large quantity of low-level waste, in the form of concrete monoliths, that are stored in large…
Type:PATRAM Proceedings
Abstract:
The spent fuel discharged from Japanese LWR will be stored as the recycled-fuel-resources in an interim storage facility. The cask storage…
Type:PATRAM Proceedings
Abstract:
The regulations governing the transport of radioactive materials are prepared by the International Atomic Energy Agency (IAEA), with the…
Type:PATRAM Proceedings
Abstract:
This report describes the extension of the validation of previous plane strain finite element analysis (FEA) model results presented in…
Type:PATRAM Proceedings
Abstract:
According to International Atomic Energy Agency (IAEA) regulations, transport containers for spent fuel must be constructed to prevent…
Type:PATRAM Proceedings
Abstract:
Kobe Steel, Ltd. has been producing enriched boron-10 from the spring of 2001, and the unique manufacturing process of borated aluminum…
Type:PATRAM Proceedings
Abstract:
A guide material to introduce the burnup credit in Japan has been prepared and published in the name of a Guide Introducing Burnup Credit,…