Resources

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Comparison of Pad Hardness Study With Drop Test Results
Type:PATRAM Proceedings
Author(s):Robert E. Nickell, Y.R. Rashid
Abstract:
Title 10, Part 71, of the Code of Federal Regulations (10 CFR 71) contains requirements for the construction and operation of spent nuclear…
Compliance Assurance and Regulatory Agency's Co-operation in the UK (Benefits Resulting from Co-operation Between the UK Regulatory Enforcing Agencies and the Use of Quality Assurance as a Method of Assuring Compliance)
Type:PATRAM Proceedings
Author(s):C.J. Pecover, B.C. Ross
Abstract:
The impact of the 1985 Edition of IAEA - REGULATIONS FOR THE SAFE TRANSPORT OF RADIOACTIVE MATERIAL - SAFETY SERIES NO 6 (1985) on the…
Containers Analysis Code of Zero Order (CACOO)-A Basic Design System for Type B Packages
Type:PATRAM Proceedings
Author(s):C. Gaspar, G. Benito, J.C. Rey
Abstract:
Very frequently, the principal iSsues that have to be assesed in the design of a type B(U) package are radiation shielding and evaluation…
Containment of Radioactive Powders by Seals
Type:PATRAM Proceedings
Author(s):J. Higson, R.J. Moulton, RA Vaughan
Abstract:
Safety regulations require that the possible loss of radioactive material from a packaging is restricted to very low levels for both normal…
Contribution to Internal Pressure and Flammable Gas Concentration in RAM Transport Packages*
Type:PATRAM Proceedings
Author(s):M.M. Warrant, N. Brown
Abstract:
Various facilities in the U. S. operated by the U.S. Department of Energy generate wastes contaminated with transuranic (TRU) isotopes (…
Criticality Benchmarks for COG: A New Point-Wise Monte Carlo Code
Type:PATRAM Proceedings
Author(s):H.P. Alesso, J. Pearson, J.S. Choi
Abstract:
COO is a new point-wise Monte Carlo code being developed and tested at LLNL for the Craycomputer. It solves the Boltzmann equation for the…
Current Status of Nuclear Materials Transportation in Japan
Type:PATRAM Proceedings
Author(s):S. Aoki, M. Tanabe, R. Tanino, S. Fukuda
Abstract:
Some 30 years have passed since the development and utilization of nuclear power began on a fullscale. During that time, the nuclear power…
Demographic and Transportation Parameters in RADTRAN*
Type:PATRAM Proceedings
Author(s):J.D. Brogan, J. W. Cashwell, K. S. Neuhauser
Abstract:
Recent efforts at Sandia National Laboratories have focused not only on modification of the RADTRAN transportation risk analysis code but…
Design and Testing of the TN-Gemini Packaging
Type:PATRAM Proceedings
Author(s):T. Neider, K. Margotta, G. V. Guerra
Abstract:
During Kay of 1987, Transnuclear began the design of the TH-Cemini, a packaging to transport contact handled transuranic radioactive waste…
Design and Testing of TRUPACT-11
Type:PATRAM Proceedings
Author(s):P.C. Gregory, S.A. Porter
Abstract:
TRUPACT-II is a reusable shipping package for U.S. Department of Energy (DOE) contacthandled transuranic (CH-TRU) waste; designed in…
Design Aspects of Plutonium Air-Transportable Packages*
Type:PATRAM Proceedings
Author(s):G.C. Allen, J.L. Moya, J. D. Pierce, S.W. Attaway
Abstract:
Recent worldwide interest in transporting plutonium powders by air has created a need for expanding the packaging technology base as well…
Design Basis for Resistance to Shock and Vibration*
Type:PATRAM Proceedings
Author(s):R. E. Glass, K. W. Gwinn
Abstract:
Sandia National Laboratories, in conjunction with its participation in the American National Standards Institute (ANSI) writing groups, has…
Design Considerations for an On-Site Spent Fuel Transfer System
Type:PATRAM Proceedings
Author(s):R.H. Jones, C.R. Jones, R.W. Lambert
Abstract:
The use of large casks (e.g., 100 - 125 tons) for the storage or shipping of spent nuclear fuel has been shown to yield operational and…
Design Features of the MK A2 Flask
Type:PATRAM Proceedings
Author(s):I.A. Wood, M. Blackbourn, D.K. Jones
Abstract:
GEC Energy Systems Limited were commissioned by CEGB to undertake the design and development of a new AGR Irradiated Fuel Transport Flask.…
Design of a New Air-Transportable Plutonium Container
Type:PATRAM Proceedings
Author(s):A.B. Thomas, M. Carr
Abstract:
Transport of Plutonium arising from reprocessing plants and the transport of fresh fuel, mixed plutonium and uranium oxide (MOX) and fast…
Design Verification Testing*
Type:PATRAM Proceedings
Author(s):M.M. Madsen, W.L. Uncapher
Abstract:
Type B packagings for transporting radioactive materials are required to survive exposures to environments in accordance with provisions of…
Design, Analysis, and Testing of Wood Filled Impact Limiters
Type:PATRAM Proceedings
Author(s):D.J. Nolan, A.G. Eggers, P. Shih
Abstract:
In current practice, Type B packagings are generally provided with protective covers or impact limiters designed to protect the cask body…
Developing a New Generation of Spent Fuel Casks
Type:PATRAM Proceedings
Author(s):William H. Lake
Abstract:
The Department of Energy (DOE) has been authorized under the 1982 Nuclear Waste Policy Act (NWPA), and its 1987 amendment to develcp a…
Development of a Concrete Container for Irradiated Fuel Storage and Transport
Type:PATRAM Proceedings
Author(s):J.D. Tulk, R.N. Sumar
Abstract:
Ontario Hydro generates more than 67 million MWe-h/year from its 16 nuclear reactors. These reactors are all of the CANDU type and make use…
Development of a Dynamic Finite Element Computer Code for the Inelastic Analysis of Cask Structures-Pronto 3D
Type:PATRAM Proceedings
Author(s):L.M. Taylor, D.P. Flanagan, S.W. Attaway, H.R. Yoshimura
Abstract:
Dynamic analyses of radioactive material packagings require accurate three-dimensional models of impact and puncture events. PRONTO 30, a…