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A STATUS REPORT ON THE REVIEW AND REVISION OF THE INTERNATIONAL ATOMIC ENERGY AGENCY’S REGULATIONS FOR THE SAFE TRANSPORT OF RADIOACTIVE MATERIAL
Type:PATRAM Proceedings
Author(s):Gerry J. Dicke, Ronald B. Pope, Richard Boyle
Abstract:
The International Atomic Energy Agency (IAEA) last published its Regulations for the Safe Transport of Radioactive Materials(Transport…
A TRANSPORT / STORAGE CASK TAILORED TO JAPANESE NEED: THE TK 69 CASK
Type:PATRAM Proceedings
Author(s):C. Vallentin, H. TANIUCHI, H. Akamatsu
Abstract:
Within the back end management, dry interim storage especially directly on the Nuclear Power Plant site is one solution. Therefore, it is a…
A Transportation Risk Assessment Tool for Analyzing the Transport of Spent Nuclear Fuel and High-Level Radioactive Waste to the Proposed Yucca Mountain Repository
Type:PATRAM Proceedings
Author(s):Dr. Thomas I. McSweeney, Thomas Winnard, Steven Ross, Ralph E. Best
Abstract:
The Yucca Mountain Transportation Database was developed as a data management tool for assembling and integrating data from multiple…
A Web-Site to Demonstrate the Safety of Radioactive Material Transportation Packages
Type:PATRAM Proceedings
Author(s):Mona L. Aragon, Douglas J Ammerman, K. Sieglinde Neuhauser, Patricia Armijo DOE, Ashok Kapoor DOE
Abstract:
The U.S. Department of Energy National Transportation Program (NTP) is committed to dissemination of accurate and reliable information…
A WORLDWIDE ASSESSMENT OF THE TRANSPORT OF IRRADIATED NUCLEAR FUEL AND HIGH-LEVEL WASTE
Type:PATRAM Proceedings
Author(s):M.T.M. Brittinger, Ronald B. Pope, Xavier Bernard-Bruls
Abstract:
The Secretariat of the International Atomic Energy Agency recently undertook informal contacts with many of the countries and organizations…
Accuracy Evaluation of Reactor Records based on Solution Analyses Data of Spent Fuels at JNC Tokai Reprocessing Plant
Type:PATRAM Proceedings
Author(s):Ishi Mitsuhashi, Mitsuro Matsumoto, Masanori Ebihara
Abstract:
A series of 235U residual enrichment of reactor records, which affects reactivity of individual fuel assembly directly, were compared with…
ADVANCED NUHOMSâ SYSTEM Solution For Spent Fuel Storage At High Seismic Activity ISFSI Sites
Type:PATRAM Proceedings
Author(s):B. Grubb, M. Manrique, I. McInnes, A. Gantayat
Abstract:
The standard NUHOMSâ System licensed under Certificate of Compliance (CoC) 72-1004, stores PWR and BWR spent fuel assemblies in sealed…
Alternative Thermal Test of a Transport Package in a Laboratory Facility
Type:PATRAM Proceedings
Author(s):Sharon L. Williamson, Fred Taylor
Abstract:
This paper describes an oil-fired burner test apparatus at General Plastics Manufacturing Company in Tacoma, Washington and the results of…
An Experimental Investigation of Thermal Stratification in Water-Filled Flasks
Type:PATRAM Proceedings
Author(s):C J Fry
Abstract:
Transport flasks are often filled with water as it provides both good cooling and shielding for irradiated fuel. However, during a fire,…
AN OVERVIEW OF THE INTERNATIONAL ATOMIC ENERGY AGENCY’S TRANSPORT SAFETY PROGRAMME
Type:PATRAM Proceedings
Author(s):Ronald Pope, Gerry Dicke, Xavier Bernard Bruls, M. T. Brittinger
Abstract:
Following creation in the 1950s of the International Atomic Energy Agency (IAEA), the development of model regulations to provide for the…
ANALYSIS METHOD ON THE 9M DROP IMPACT OF SPENT FUEL SHIPPING CASKS USING ABAQUS AND LS-DYNA3D
Type:PATRAM Proceedings
Author(s):Young-Shin Lee Lee, Chung-Hyun Ryu, Jae-Hyung Lee, Jae-Yun Na, Yong Jae Kim
Abstract:
Various analysis codes have been used for the 9m drop impact analysis of nuclear fuel casks, and analysis results are usually compared with…
ANALYSIS OF MAXIMUM REASONABLY FORESEEABLE ACCIDENTS FOR THE YUCCA MOUNTAIN DRAFT ENVIRONMENTAL IMPACT STATEMENT (DEIS)
Type:PATRAM Proceedings
Author(s):Steven B. Ross, Ralph E. Best, Steven J. Maheras, Dr. Thomas I. McSweeney
Abstract:
Accidents could occur during the transportation of spent nuclear fuel and high-level radioactive waste. This paper describes the risks and…
ANALYSIS OF THE EFFECTS OF PIPELINE AND RAILROAD FIRES ON LEGAL WEIGHT TRUCK TRANSPORTATION CASKS
Type:PATRAM Proceedings
Author(s):Carlos Lopez, Jorman A. Koski
Abstract:
Questions specific to the safety of rail transportation of spent nuclear fuel have been raised. The purpose of this paper is to examine the…
Analytical, Numerical and Experimental Investigations on the Impact Behaviour of Packagings for the Transport of Radioactive Material under Slap Down Conditions
Type:PATRAM Proceedings
Author(s):T. Quercetti, Viktor Ballheimer, G. Wieser
Abstract:
This paper decribes a methodical way to find critical drop angles or better a range of drop angles for oblique drops of a packages used for…
ANF-10: A New Transport Container for Fresh BWR Fuel Assemblies According to IAEA Requirements
Type:PATRAM Proceedings
Author(s):W. Jahreiß, U. Philippczyk, W. Paulinyi, J.-P. Masslowski
Abstract:
The shipment of non-irradiated BWR uranium fuel assemblies (including enriched reprocessed uranium or ERU) as well as BWR and PWR fuel rods…
ANF-18/MOX: A Modular Transport System for Fresh PWR MOX Fuel Assemblies
Type:PATRAM Proceedings
Author(s):W. Jahreiß, B. Brzoska, W. Bergmann, B. Gogolin
Abstract:
For the shipment of non-irradiated PWR mixed oxide (MOX) fuel assemblies from the fabrication facility to the power plant, the new ANF-18/…
ANF-18: A New Transport Container for Fresh PWR Fuel Assemblies According to IAEA Requirements
Type:PATRAM Proceedings
Author(s):W. Jahreiß, U. Philippczyk, W. Paulinyi, T. Quercetti
Abstract:
The shipment of non-irradiated PWR uranium fuel assemblies (including enriched reprocessed uranium or ERU) from the fabrication facility to…
APPLICABILITY OF THE MONTE CARLO METHOD TO THE EVALUATION OF DOSE EQUIVALENT RATES FROM METAL CASKS IN AN INTERIM STORAGE FACILITY
Type:PATRAM Proceedings
Author(s):D. Ito, A. Terada, S. Mitake
Abstract:
Dose equivalent rates at the premises of an interim storage facility have been evaluated by using the continuous energy Monte Carlo code…
Application of Laser-Manufacturing Technology to Fabricate Square Tubes for Multi-Purpose Canister
Type:PATRAM Proceedings
Author(s):Takeshi Aboshi, Koutaro Fujimoto, Takashi Kawahara, Akikazu KITAGAWA, Naoaki Fukuda, Sinnosuke Takeda, Ryoji ASANO
Abstract:
The UMS/MPC transport/storage system developed by NAC International consists of a multi-purpose canister that is called the Transportable…
APPLYING ALARA TO THE DECONTAMINATION OF IRRADIATED NUCLEAR FUEL CONTAINERS
Type:PATRAM Proceedings
Author(s):J. S. Hughes, K. B. Shaw, G. Schwarz, H-J. Fett, Y. François, N. Dellero, B. Tchatalian, J. van Hienen, R. Jansma, C. Lefaure, J-P. Degrange, R. Gelder
Abstract:
Prior to shipment, the levels of non-fixed contamination on the surface of packages containing radioactive materials must be less than the…