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Spent fuel cladding corrosion under tuff repository conditions: initial observations

Description: The Westinghouse Hanford Company program is investigating corrosion and stress corrosion cracking of Zircaloy-2 and 4 in two model tuff repository environments using an experimental approach in which the repository environment is reproduced as accurately as possible, including temperature, radiation field, water chemistry and materials associations. Post-experimental sample evaluation utilizes or will utilize sophisticated SEM/STEM, Auger surface analysis/ion milling, and trace element release … more
Date: June 1, 1985
Creator: Smith, H.D. & Oversby, V.M.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Nevada Nuclear Waste Storage Investigations: exploratory shaft. Phase I. Conceptual design report

Description: It is proposed that an Exploratory Shaft (ES) be constructed in Yucca Mountain on or near the southwest portion of the Nevada Test Site (NTS) as part of the Nevada Nuclear Waste Storage Investigations. This document describes a conceptual design for an ES and a cost estimate based on a set of construction assumptions. Included in this document are appendixes consisting of supporting studies done at NTS by Fenix and Scisson, Inc. and Holmes and Narver, Inc. These appendixes constitute a history … more
Date: June 1, 1982
Creator: Nelson, D. C.; Merson, T. J.; McGuire, P. L. & Sibbitt, W. L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Permeability and pore-fluid chemistry of the Bullfrog Tuff in a temperature gradient: summary of results

Description: In order to study the changes that take place with time when groundwater comes in contact with heated rock, and to determine the ease with which potential radionuclide-bearing groundwater could be carried into the environment, the permeability and fluid chemistry of the Bullfrog Tuff from Yucca Mountain were studied under conditions simulating a nuclear waste repository environment. (ACR)
Date: June 1, 1983
Creator: Byerlee, J.; Morrow, C. & Moore, D.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Salt repository project closeout status report

Description: This report provides an overview of the scope and status of the US Department of Energy (DOE`s) Salt Repository Project (SRP) at the time when the project was terminated by the Nuclear Waste Policy Amendments Act of 1987. The report reviews the 10-year program of siting a geologic repository for high-level nuclear waste in rock salt formations. Its purpose is to aid persons interested in the information developed during the course of this effort. Each area is briefly described and the major ite… more
Date: June 1, 1988
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Post-test thermal calculations and data analyses for the Spent Fuel Test, Climax

Description: After the Spent Fuel Test - Climax (SFT-C) was completed, additional calculations were performed using the best available (directly measured or inferred from measurements made during the test) input parameters, thermal properties, and power levels. This report documents those calculations and compares the results with measurements made during the three-year heating phase and six-month posttest cooling phase of the SFT-C. Three basic types of heat-transfer calculations include a combined two-dim… more
Date: June 1, 1986
Creator: Montan, D. N. & Patrick, W. C.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Tuff reaction vessel experiment

Description: A laboratory leaching test has been performed as part of a project to evaluate the suitability of tuff rocks at Yucca Mountain, Nevada, as a site for a high-level nuclear waste repository. Glass samples of the kind that will be used to store nuclear waste were placed in water inside tuff vessels, and then the tuff vessels were placed in water inside Teflon containers. Glass-component leach rates and migration through the tuff were measured for samples of the ATM-8 actinide glass, which is a PNL… more
Date: June 1, 1986
Creator: Bazan, F. & Rego, J.H.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Yucca Mountain Site Characterization Project bibliography, 1992--1994. Supplement 4

Description: Following a reorganization of the Office of Civilian Radioactive Waste Management in 1990, the Yucca Mountain Project was renamed Yucca Mountain Site Characterization Project. The title of this bibliography was also changed to Yucca Mountain Site Characterization Project Bibliography. Prior to August 5, 1988, this project was called the Nevada Nuclear Waste Storage Investigations. This bibliography contains information on this ongoing project that was added to the Department of Energy`s Energy … more
Date: June 1, 1992
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Climax spent fuel dosimetry. Short term exposure, 8 March 1983

Description: The second short-term exposure (performed 8 March 1983) in Hole CFH3 at the Climax Spent Fuel Test site is described. These short-term (1 hour long) exposures are intended to provide an independent measurement of the exposure rate at the wall and the 0.51-m and 0.66-m locations. Only CaF{sub 2} TLD`s were used in the second short-term exposure. Harshaw chips were cut to 0.32 x 0.18 x 0.09 cm size and aged by several exposure/readout/bakeout cycles until all odd chips were weeded out and the rem… more
Date: June 1, 1984
Creator: Quam, W. & DeVore, T.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Analysis of fracturing in hole UG-2 Spent Fuel Test-Climax

Description: Detailed fracture logging and analysis of the UG-2 core from the Climax Stock is reported. This borehole is about 183 m long (600 ft) and slants downward below the Spent Fuel Test workings, thus representing the only sampling of the quartz monzonite at depth. An effective means of orienting the core sections relative to a certain joint set of known orientation is demonstrated, and a computational procedure for accomplyishing this in non-vertical boreholes is presented. Although this core orient… more
Date: June 1, 1984
Creator: Thorpe, R.K.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Public information circular for shipments of irradiated reactor fuel. Revision 4

Description: This publication is the fifth in a series of annual publications issued by the Nuclear Regulatory Commission in response to public information requests regarding the Commission`s regulation of shipments of irradiated reactor fuel. This publication contains basically three kinds of information: (1) routes recently approved (18 months) by the Commission for the shipment of irradiated reactor fuel; (2) information regarding any safeguards-significant incidents that may be (to date none have) repor… more
Date: June 1, 1984
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Spent fuel test. Climax data acquisition system integration report

Description: The Spent Fuel Test - Climax (SFT-C) is a test of the retrievable, deep geologic storage of commercially generated, spent nuclear reactor fuel in granitic rock. Eleven spent fuel assemblies, together with 6 electrical simulators and 20 guard heaters, are emplaced 420 m below the surface in the Climax granite at the Nevada Test Site. On June 2, 1978, Lawrence Livermore National Laboratory (LLNL) secured funding for the SFT-C, and completed spent fuel emplacement May 28, 1980. This multi-year dur… more
Date: June 1, 1982
Creator: Nyholm, R. A.; Brough, W. G. & Rector, N. L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Climax spent fuel dosimetry. Progress report, September 1982-January 1984

Description: This report covers work done during FY83. These tasks included: (1) recovery and readout of the final set of dosimeters from the Climax facility, (2) a calibration exposure at the Sandia Gamma Irradiation Facility (GIF) to verify temperature effects during irradiation, and (3) a recalculation of new and existing calibration data over the range of 2 x 10{sup 3} to 10{sup 8} rads-LiF. This new set of calibration data is slightly different from that previously reported, and incorporates the best t… more
Date: June 1, 1984
Creator: Quam, W. & DeVore, T.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Mined Geologic Disposal System Concept of Operations

Description: A Concept of Operations has been developed for the disposal of high-level radioactive waste in the potential geologic repository at Yucca Mountain. The Concept of Operations has been developed to document a cormion understanding of how the repository is to be operated. It is based on the repository architecture identified in the Initial Summary Report for Repository/Waste Package Advanced Conceptual Design and describes the operation of the repository from the initial receipt of waste through r… more
Date: June 8, 1995
Creator: Heidt, R. M.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Review of waste package verification tests. Semiannual report, April 1984-September 1984. Volume 5

Description: This ongoing study is part of a task to specify tests that may be used to verify that engineered waste package/repository systems comply with NRC radionuclide containment and controlled release performance objectives. Work covered in this report includes crushed tuff packing material for use in a high level waste tuff repository. A review of available tests to quantify packing performance is given together with recommendations for future testing work. 27 refs., 6 figs., 3 tabs.
Date: June 1, 1985
Creator: Jain, H.; Veakis, E. & Soo, P.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Water-rock interactions and the pH stability of groundwater from Yucca Mountain, Nevada

Description: Titrations of acidic solutions in waters from the tuff and carbonate aquifers at Yucca Mountain were simulated using the geochemical codes PHREEQE and EQ3/6. The simulations tested pH stability of the waters in the presence of different minerals and in their absence. Two acidic solutions, 10{sup {minus}4} HCl and 10{sup {minus}4}M UO{sub 2}(NO{sub 3}){sub 2}, were titrated in to the water. Little pH and/or compositional change resulted in the groundwater when the HCl solution was titrated, but … more
Date: June 1, 1992
Creator: Ebinger, M.H.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Estimating the water table under the Radioactive Waste Management Site in Area 5 of the Nevada Test Site: The Dupuit-Forcheimer approximation

Description: To adequately manage the low level nuclear waste (LLW) repository in Area 5 of the Nevada Test Site (NTS), a knowledge of the water table under the site is paramount. The estimated thickness of the arid intermountain basin alluvium is roughly 900 feet. Very little reliable water table data for Area 5 currently exists. The Special Projects Section of the Reynolds Electrical & Engineering Co., Inc. Waste Management Department is currently formulating a long-range drilling and sampling plan in sup… more
Date: June 1, 1992
Creator: Lindstrom, F. T.; Barker, L. E.; Cawlfield, D. E.; Daffern, D. D.; Dozier, B. L.; Emer, D. F. et al.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Modeling ion exchange in clinoptilolite using the EQ3/6 geochemical modeling code

Description: Assessing the suitability of Yucca Mtn., NV as a potential repository for high-level nuclear waste requires the means to simulate ion-exchange behavior of zeolites. Vanselow and Gapon convention cation-exchange models have been added to geochemical modeling codes EQ3NR/EQ6, allowing exchange to be modeled for up to three exchangers or a single exchanger with three independent sites. Solid-solution models that are numerically equivalent to the ion-exchange models were derived and also implemente… more
Date: June 1, 1992
Creator: Viani, B. E. & Bruton, C. J.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Yucca Mountain project container fabrication, closure and non-destructive evaluation development activities; Summary and viewgraphs

Description: In this presentation, container fabrication, closure, and non-destructive evaluation (NDE) process development activities are described. All of these activities are interrelated, and will contribute to the metal barrier selection activity. The plan is to use a corrosion-resistant material in the form of a cylinder with a wall thickness of {approximately}1cm (2cm for pure copper.) The materials under consideration include the three austenitic alloys: stainless steel-304L, stainless steel-316L an… more
Date: June 1989
Creator: Russell, E. W. & Nelson, T. A.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Preliminary calculations of release rates of Tc-99, I-129, and Np-237 from spent fuel in a potential repository in tuff

Description: This report presents preliminary calculations of time-dependent release rates of selected radionuclides from the engineered barrier system in a potential high-level waste repository in unsaturated tuff, representative of a potential repository at Yucca Mountain in southern Nevada. These results are intended for use as preliminary source terms for calculating total system performance. The radionuclides specified for preliminary release-rate calculations are Tc-99, I-129, Cs-135, and Np-237 for g… more
Date: June 1, 1990
Creator: Apted, M. J.; O`Connell, W. J.; Lee, K. H.; MacIntyre, A. T.; Ueng, T. S.; Lee, W. W. L. et al.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Department of Energy Programmatic Spent Nuclear Fuel Management and Idaho National Engineering Laboratory Environmental Restoration and Waste Management Programs Draft Environmental Impact Statement; Volume 1, Appendix F, Nevada Test Site and Oak Ridge Reservation Spent Nuclear Fuel Management Programs

Description: This volume addresses the interim storage of spent nuclear fuel (SNF) at two US Department of Energy sites, the Nevada Test Site (NTS) and the Oak Ridge Reservation (ORR). These sites are being considered to provide a reasonable range of alternative settings at which future SNF management activities could be conducted. These locations are not currently involved in management of large quantities of SNF; NTS has none, and ORR has only small quantities. But NTS and ORR do offer experience and infr… more
Date: June 1, 1994
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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The effect of rock-water interaction on permeability

Description: Current investigations for managing high-level nuclear wastes focus on studying deep geologic repositories. The Yucca Mountain Site Characterization Project of the US Department of Energy conducts studies on Yucca Mountain, Nevada, to determine its suitability as a potential high-level nuclear waste repository. The potential host rock in Yucca Mountain is a layer of devitrified Topopah Spring tuff that is densely welded, fractured, and lithophysae-poor. The suitability of a potential nuclear wa… more
Date: June 1, 1995
Creator: Lin, Wunan; Roberts, J. J.; Glassley, W. & Ruddle, D.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Stress corrosion cracking of candidate waste container materials; Final report

Description: Six alloys have been selected as candidate container materials for the storage of high-level nuclear waste at the proposed Yucca mountain site in Nevada. These materials are Type 304L stainless steel (SS). Type 316L SS, Incoloy 825, phosphorus-deoxidized Cu, Cu-30%Ni, and Cu-7%Al. The present program has been initiated to determine whether any of these materials can survive for 300 years in the site environment without developing through-wall stress corrosion cracks. and to assess the relative … more
Date: June 1, 1992
Creator: Park, J. Y.; Maiya, P. S.; Soppet, W. K.; Diercks, D. R.; Shack, W. J. & Kassner, T. F.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Yucca Mountain Site Characterization Project Technical Data Catalog (quarterly supplement)

Description: The June 1, 1985, Department of Energy (DOE)/Nuclear Regulatory Commission (NRC) Site-Specific Procedural Agreement for Geologic Repository Site Investigation and Characterization Program requires the DOE to develop and maintain a catalog of data which will be updated and provided to the NRC at least quarterly. This catalog is to include a description of the data; the time (date), place, and method of acquisition; and where it may be examined. The Yucca Mountain Site Characterization Project (Y… more
Date: June 30, 1993
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Results from Nevada Nuclear Waste Storage Investigations (NNWSI) Series 3 spent fuel dissolution tests

Description: The dissolution and radionuclide release behavior of spent fuel in groundwater is being studied by the Yucca Mountain Project (YMP), formerly the Nevada Nuclear Waste Storage Investigations (NNWSI) Project. Specimens prepared from pressurized water reactor fuel rod segments were tested in sealed stainless steel vessels in Nevada Test Site J-13 well water at 85{degree}C and 25{degree}C. The test matrix included three specimens of bare-fuel particles plus cladding hulls, two fuel rod segments wit… more
Date: June 1, 1990
Creator: Wilson, C. N.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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