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LWR Pressure Vessel Irradiation Surveillance Dosimetry Quarterly Progress Report: October-December 1979

Description: This report was compiled at the Hanford Engineering Development Laboratory operated by Westinghouse Hanford Company, a subsidiary of Westinghouse Electric Corpoation, for the United States Department of Energy and the Nuclear Regulatory Commission, under DOE contract number DE-AC14-76FF02170 and NRC service request number TV-0176.
Date: December 1980
Creator: Guthrie, G. L. & McElroy, W. N.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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ESTIMATES FOR RELEASE OF RADIONUCLIDES FROM POTENTIALLY CONTAMINATED CONCRETE AT THE HADDAM NECK NUCLEAR PLANT.

Description: Decommissioning of the Haddam Neck Nuclear Power Plant operated by Connecticut Yankee is in progress. Figure 1 shows a schematic of the Containment Building and Spent Fuel Pool (SFP) Building. Consideration is being given to leaving some subsurface concrete from the Containment, Spent Fuel and certain other buildings in place following NRC license termination. Characterization data of most of these structures show small amounts of residual contamination. The In-Core Sump area of the Containment… more
Date: September 15, 2004
Creator: SULLIVAN, T.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Testing of coatings for the nuclear industry

Description: Commercial scale nuclear power generating plant coatings must be able to withstand simultaneous exposure both to high humidity, and to cumulative radiation dosage, at elevated temperatures, for the design life of the plant. The coatings must be decontaminable by means other than by stripping, that is, actual physical removal, and must be of sufficient durability to withstand projected conditions of a loss of coolant accident. Tests to show that coatings are expected to do more than retard corro… more
Date: January 1, 1977
Creator: Goldberg, G.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Final report for confinement vessel analysis. Task 2, Safety vessel impact analyses

Description: This report describes two sets of finite element analyses performed under Task 2 of the Confinement Vessel Analysis Program. In each set of analyses, a charge is assumed to have detonated inside the confinement vessel, causing the confinement vessel to fail in either of two ways; locally around the weld line of a nozzle, or catastrophically into two hemispheres. High pressure gases from the internal detonation pressurize the inside of the safety vessel and accelerate the fractured nozzle or hem… more
Date: January 26, 1994
Creator: Murray, Y. D.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Demands placed on waste package performance testing and modeling by some general results on reliability analysis

Description: Waste packages for a US nuclear waste repository are required to provide reasonable assurance of maintaining substantially complete containment of radionuclides for 300 to 1000 years after closure. The waiting time to failure for complex failure processes affecting engineered or manufactured systems is often found to be an exponentially-distributed random variable. Assuming that this simple distribution can be used to describe the behavior of a hypothetical single barrier waste package, calcula… more
Date: September 1, 1991
Creator: Chesnut, D.A.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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LOFT suppression tank spray system piping: heat exchanger BS-H-31 piping modifications

Description: A stress analysis of the piping modification, resulting from relocation of heat exchanger BS-H-31 of the LOFT Blowdown Suppressing Tank Spray System, was performed. The piping, fittings, and supports were found to comply with the criteria of Section III of the ASME Boiler and Pressure Vessel Code, 1974.
Date: November 7, 1977
Creator: Blandford, R.K.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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A Multi-Layered Ceramic Composite for Impermeable Fuel Cladding for COmmercial Wate Reactors

Description: A triplex nuclear fuel cladding is developed to further improve the passive safety of commercial nuclear plants, to increase the burnup and durablity of nuclear fuel, to improve the power density and economics of nuclear power, and to reduce the amount of spent fuel requiring disposal or recycle.
Date: March 3, 2008
Creator: Feinroth, Herbert
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Dynamic testing of nuclear power plant structures: an evaluation

Description: Lawrence Livermore Laboratory (LLL) evaluated the applications of system identification techniques to the dynamic testing of nuclear power plant structures and subsystems. These experimental techniques involve exciting a structure and measuring, digitizing, and processing the time-history motions that result. The data can be compared to parameters calculated using finite element or other models of the test systems to validate the model and to verify the seismic analysis. This report summarizes … more
Date: February 1, 1980
Creator: Weaver, H.J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Category I structures: safety margin at ultimate load

Description: The objective of the program described in this paper is to supply test information needed to assess the structural capability of Category I structural systems that are loaded beyond their design limits. The program activities were started in the latter half of FY 1980. The activities for FY 1981 are to continue the development of structural test plans, initiate design, construction and testing of small structures, continue to develop and perform analytical prediction of limit states, and to com… more
Date: January 1, 1980
Creator: Anderson, C. A.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Facilities design for TIBER II

Description: This paper describes the conceptual design of the reactor building and reactor maintenance building for the TIBER II tokamak. These buildings are strongly influenced by the reactor configuration, and their characterization allows a better understanding of the economic and technical implications of the reactor design. Key features of TIBER II that affect the facilities design are the small size and compact arrangement, the use of an external vacuum vessel, and the complete reliance on remote mai… more
Date: January 1, 1987
Creator: Thomson, S. L. & Blevins, J. D.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Radiation Shielding Materials and Containers Incorporating Same

Description: An improved radiation shielding material and storage systems for radioactive materials incorporating the same. The PYRolytic Uranium Compound (''PYRUC'') shielding material is preferably formed by heat and/or pressure treatment of a precursor material comprising microspheres of a uranium compound, such as uranium dioxide or uranium carbide, and a suitable binder. The PYRUC shielding material provides improved radiation shielding, thermal characteristic, cost and ease of use in comparison with o… more
Date: November 1, 2005
Creator: Mirsky, Steven M.; Krill, Stephen J. & Murray, Alexander P.
Item Type: Refine your search to only Text
Partner: UNT Libraries Government Documents Department
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Lance water injection tests adjacent to the 281-3H retention basin at the Savannah River Site, Aiken, South Carolina

Description: A pilot-scale field demonstration of waste isolation using viscous- liquid containment barriers has been planned for the 281-3H retention basin at the Savannah River Site, Aiken, SC. The 281-3H basin is a shallow retention/seepage basin contaminated mainly by radionuclides. The viscous-liquid containment barrier utilizes the permeation of liquid grout to either entomb the contaminants within a monolithic grout structure or to isolate the waste by drastically reducing the permeability, of the so… more
Date: September 1, 1996
Creator: Freifeld, B.; Myer, L.; Moridis, G.; Cook, P.; James, A.; Pellerin, L. et al.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Shipment of Small Quantities of Unspecified Radioactive Material in Chalfant Packagings

Description: In the post 6M era, radioactive materials package users are faced with the disciplined operations associated with use of Certified Type B packagings. Many DOE, commercial and academic programs have a requirement to ship and/or store small masses of poorly characterized or unspecified radioactive material. For quantities which are small enough to be fissile exempt and have low radiation levels, the materials could be transported in a package which provides the required containment level. Because… more
Date: June 12, 2009
Creator: Smith, Allen; Abramczyk, Glenn; Nathan, Steven & Bellamy, Steve
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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FINITE-ELEMENT ANALYSIS OF ROCK FALL ON UNCANISTERED FUEL WASTE PACKAGE DESIGNS (SCPB: N/A)

Description: The objective of this analysis is to explore the Uncanistered Fuel (UCF) Tube Design waste package (WP) resistance to rock falls. This analysis will also be used to determine the size of rock that can strike the WP without causing failure in the containment barriers from a height based on the starter tunnel dimensions. The purpose of this analysis is to document the models and methods used in the calculations.
Date: October 18, 1996
Creator: Ceylan, Z.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Test report for PAS-1 cask certification for shipping payload B

Description: This test report documents the successful inspection and testing to certify two NuPac PAS-1 casks in accordance with US Department of Energy Certificate of Compliance (CoC) USA/9184/B(U). The primary and secondary containment vessels of each cask met the acceptance criteria defined in the CoC and the test plan.
Date: October 13, 1998
Creator: MERCADO, J.E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Topological Galleries: A High Level User Interface for Topology Controlled Volume Rendering

Description: Existing topological interfaces to volume rendering are limited by their reliance on sophisticated knowledge of topology by the user. We extend previous work by describing topological galleries, an interface for novice users that is based on the design galleries approach. We report three contributions: an interface based on hierarchical thumbnail galleries to display the containment relationships between topologically identifiable features, the use of the pruning hierarchy instead of branch dec… more
Date: June 30, 2011
Creator: MacCarthy, Brian; Carr, Hamish & Weber, Gunther H.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Sample push out fixture

Description: This invention generally relates to the remote removal of pelletized samples from cylindrical containment capsules. V-blocks are used to receive the samples and provide guidance to push out rods. Stainless steel liners fit into the v-channels on the v-blocks which permits them to be remotely removed and replaced or cleaned to prevent cross contamination between capsules and samples. A capsule holder securely holds the capsule while allowing manual up/down and in/out movement to align each sampl… more
Date: February 22, 2000
Creator: Biernat, John L.
Item Type: Refine your search to only Patent
Partner: UNT Libraries Government Documents Department
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Heat Transfer and Thermal Stresses in Nuclear Reactor Shells

Description: A method is presented for determining heat transfer rates and thermal stresses from the gamma-ray energy absorption of nuclear reactor shells for plane, cylindrical, and spherical geometries. Criteria for minimizing thermal stresses are developed, along with the corresponding external cooling rates necessary to minimize the thermal stress. Design charts are presented for rapid determination of approximate thermal stresses and heat transfer rates, along with a numerical example illustrating the … more
Date: September 1953
Creator: Durham, Franklin P.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Surface Environmental Surveillance Procedures Manual

Description: Environmental surveillance data are used in assessing the impact of current and past site operations on human health and the environment, demonstrating compliance with applicable local, state, and federal environmental regulations, and verifying the adequacy of containment and effluent controls. SESP sampling schedules are reviewed, revised, and published each calendar year in the Hanford Site Environmental Surveillance Master Sampling Schedule. Environmental samples are collected by SESP staff… more
Date: September 20, 2000
Creator: Hanf, R. W. & Poston, T. M.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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