Resources

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Development of Cask Basket for High Burnup and MOX Spent Fuels
Type:PATRAM Proceedings
Author(s):T. Ajima, Toshiari Saegusa, Y. Inohara, A. Kosaki
Abstract:
At present, in Light Water Reactor the shift to high bumup of nuclear fuel is going on, and also the use of MOX fuel is planned (e.g.,…
Development of FBR Fuel Shipping Cask for Post-Irradiated Examination
Type:PATRAM Proceedings
Author(s):S. Uruwashi, Y. Kitai, M. Usami
Abstract:
Power Reactor and Nuclear Fuel Development Corporation will be performing the post-irradiated examination of fuel subassemblies irradiated…
Development of Inelastic Analysis Acceptance Criteria for Radioactive Material Transportation Packages
Type:PATRAM Proceedings
Author(s):D.J. Ammerman, J.S. Ludwigsen
Abstract:
The response of radioactive material transportation packages to mechanical accident loadings can be more accurately characterized by…
Development of Spent-Fuel Transport and Storage Dry Casks
Type:PATRAM Proceedings
Author(s):K. Maruoka, Hiroki TAMAKI
Abstract:
Many nuclear power plants are running out of storage space in their reactor pools for storing spent fuel. On-site spent fuel storage in…
Development of the Packaging for Tritium Transport
Type:PATRAM Proceedings
Author(s):K. Okuno, Y. Matsuda, M. Ohashi, Suguru Hode
Abstract:
For the purpose of establishment of the Fusion Fuel Cycle, research and development using tritium has been carryied out by Japan Atomic…
Developments in Spent Fuel Storage
Type:JNMM
Volume:23
Issue:3
Author(s):Richard A. Stallings
Abstract:
It's good to be back again. I was here one year ago and saw a part of Washington I had never seen before, even in the eight years I…
DIRECT CONVERSION OF PLUTONIUM-CONTAINING MATERIALS TO BOROSILICATE GLASS FOR STORAGE OR DISPOSAL
Type:Annual Meeting Proceedings
Author(s):C. W. Forsberg, E. C. Beahm
Abstract:
A new process, the Glass Material Oxidation and Dissolution System (GMODS), has been invented for the direct conversion of plutonium metal…
DISPOSITION OF SURPLUS FISSILE MATERIALS VIA IMMOBILIZATION
Type:Annual Meeting Proceedings
Author(s):Leonard W. Gray, Tehmau Kan, William G. Sutcliffe, J. Malvyn McKibben, William Danker
Abstract:
In the Cold War aftermath, the U. S. and Russia have agreed to large reductions in nuclear weapons. To aid in the selection of long-term…
DOE/ABACC SAFEGUARDS COOPERATION
Type:Annual Meeting Proceedings
Author(s):J. Michael Whitaker, Carlos Feu Alvim
Abstract:
In 1994, the U.S. Department of Energy (DOE) and the Brazilian-Argentine Agency for Accounting and Control of Nuclear Materials (ABACC)…
Dose Rate Calculations for Transport of Vitrified Residues by Sea·
Type:PATRAM Proceedings
Author(s):M.H. Dean, M.R. Lingard
Abstract:
It is planned that vitrified residues (high level waste, (HLW)) from fuel reprocessing operations in Europe will be transported in purpose-…
Drop Testing of Packages Using Scale Models·
Type:PATRAM Proceedings
Author(s):G.C. Mok, R.W. Carlson, S.C. Lu, L.E. Fischer
Abstract:
International and U.S regulations require that a package used for transporting radioactive materials maintain containment, shielding and…
Drop Tests of Type-R Packaging Under -40° C Conditions
Type:PATRAM Proceedings
Author(s):M. Miyazawa, K. Tsuboi, K. Akashi, M. Sato, T. Koganezawa, T. Niiho, K. Asada, H. Kanazawa, M. Ohashi
Abstract:
The 1985 edition of the IAEA regulations(IAEA 1985) for the safe transport of radioactive material has invalidated the previously approved…
Drop-Test Energy Balance by Computer-Graphics Analysis of High-Speed Videotape
Type:PATRAM Proceedings
Author(s):T.R. Bump, R.D. Carlson
Abstract:
This activity was prompted by the concurrent arrival of two items at our Department of Energy Safety Analysis Report for Packaging (DOE…
Drop-Test Program With the German \"POLLUX\" Cask for Final Disposal of Spent Fuel
Type:PATRAM Proceedings
Author(s):B. Gogolin, B. Droste, T. Quercetti
Abstract:
A fullscale prototype cask for shipping, interim storage and final disposal of spent fuel in a German repository, named POLLUX, designed…
Dry Spent-Fuel Transfer System Design
Type:PATRAM Proceedings
Author(s):R. Lambert, L. Stewart, G. V. Guerra, D. Dawson
Abstract:
EPRI has had a continuing interest in developing a fuel transfer capability with the initial interest targeted at improved storage…
EFFECT OF MINOR COMPONENTS ON VITRIFICATION OF LOW-LEVEL SIMULATED NUCLEAR WASTE GLASSES
Type:Annual Meeting Proceedings
Author(s):John G, Darab, Hong Li
Abstract:
Solubility of minor components (Cl, F, P2O5, SO3, and Cr2O3) in low-level waste (LLW) glasses were determined. The dependency of solubility…
EFFECTIVE TRAINING METHODOLOGY
Type:Annual Meeting Proceedings
Author(s):Berry Crain Jr.
Abstract:
Training has become an important part of facility operation in the Department of Energy (DOE) complex. Ongoing changes in DOE requirements…
Effects of Hanford Tank Simulant Waste on Plastic Packaging Components•
Type:PATRAM Proceedings
Author(s):P. J. Nigrey, T. G. Dickens
Abstract:
The purpose of hazardous and radioactive materials packaging is to enable these materials to be transported without posing a threat to the…
Emergency Preparedness as Addressed by the WIPP Transportation System
Type:PATRAM Proceedings
Author(s):T.R. Ward, S.C. Kouba, O.R. Spooner
Abstract:
When the Department of Energy (DOE) developed the initial transportation program for the transport oftransuranic (TRU) waste to the Waste…
Emergency Response for Damaged UF6 Cylinders During Transport or Handling Activities on Site by Developing and Updating of Patch Systems
Type:PATRAM Proceedings
Author(s):E.F.M. Steinebach
Abstract:
Transportation of all goods contains the risk of an accident. Dangerous goods --like UF 6 cylinders-- are in principle not excepted from…