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:Criticality safety studies are reviewed related to Advisory Material for 1996 Edition of the IAEA Regulation for the Safe Transport of…
Type:PATRAM Proceedings
Abstract:The results of the TNDSFP Code for thermo-nuclear design of spent fuel elements package are presented in this investigation. The code…
Type:PATRAM Proceedings
Abstract:The transport of low enrichment unirradiated PwR fuel involves no criticality risk in the absence of water. However, an adequate sub-…
Type:Annual Meeting Proceedings
Abstract:The Criticality Tester (CT) became an IAEA routine inspection device in 1997. It consists of a neutron detector with preamplifier, a multi-…
Type:Annual Meeting Proceedings
Abstract:As more NDA instrumentation is being added at facilities, cross calibration of the instrumentation is becoming increasingly important.…
Type:Annual Meeting Proceedings
Abstract:Cryptographic authentication has recently become a critical component of data surety and access control within Safeguards organizations.…
Type:Annual Meeting Proceedings
Abstract:Worldwide inventories of separated civil plutonium have been increasing for a number of years. Since a relatively small quantity of…
Type:PATRAM Proceedings
Abstract:To decrease mechanic effect on loads being transponed, shock load limiters (dampers) are being widely used today. Usually, the materials…
Type:Annual Meeting Proceedings
Abstract:The main purpose of Recycle Equipment Test Facility (RETF) is to carry out hot demonstration tests on advanced equipment for the future…
Type:PATRAM Proceedings
Abstract:This paper contains the results of mechanical and thermophysical properties investigations of the dense and porous refractory concretes(…
Type:PATRAM Proceedings
Abstract:TN 17/2 transport packaging units that have been used for the transportation of irradiated fuel are contaminated internally. They have to…
DEMONSTRATION TEST FOR A SHIPPING CASK TRANSPORTING HIGHT BURN-UP SPENT FUEL -Drop Test and Analysis
Type:PATRAM Proceedings
Abstract:The drop tests stipulated in the IAEA Transport Regulation and analysis against the tests were carried out for a test package which has the…
Type:PATRAM Proceedings
Abstract:The thermal test stipulated by the lAEA transport regulations was carried out for a test package, which has the same structural features as…
Type:PATRAM Proceedings
Abstract:The video tape contains the pictures of the demonstration test of a shipping cask for high bumup spent fuels by CRIEPI that is a part of…
Type:PATRAM Proceedings
Abstract:Natural Uranium Hexafluoride (UF6 ) is transported in a steel container called 48Y-cylinder. Up to now, various safety experimental and…
Type:PATRAM Proceedings
Abstract:This paper presents the overview of the U.S. Department of Energy's (DOE) National Transportation Program (NTP). The program was recently…
Type:Annual Meeting Proceedings
Abstract:As part of the joint U.S. and Republic of Kazakhstan nuclear Material Protection, Control, and Accounting (MPC&A) program, the U.S.…
Type:Annual Meeting Proceedings
Abstract:As part of the Cooperative Threat Reduction Nuclear Material Protection, Control, and Accounting (MPC&A) Program, the US Department of…
Type:PATRAM Proceedings
Abstract:This paper summarises the design and approval testing of a new family ofTypeA and Type-B medium-size container. It also discusses some of…
Type:PATRAM Proceedings
Abstract:This paper summarises the design and approval resting ofthe Transhield-20 Type-B container in a programme that began in 1991 when the UKAEA…