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ESF BLAST DESIGN ANALYSIS

Description: The purpose and objective of this design analysis are to develop controls considered necessary and sufficient to implement the requirements for the controlled drilling and blasting excavation of operations support alcoves and test support alcoves in the Exploratory Studies Facility (ESF). The conclusions reached in this analysis will flow down into a construction specification ensuring controlled drilling and blasting excavation will be performed within the bounds established here.
Date: March 13, 1995
Creator: Fitch, E. F.
Partner: UNT Libraries Government Documents Department
open access

MINED GEOLOGIC DISPOSAL SYSTEM (MGDS) MONITORING & CONTROL SYSTEMS CENTRALIZATION TECHNICAL REPORT

Description: The objective of this report is to identify and document Mined Geologic Disposal System (MGDS) requirements for centralized command and control. Additionally, to further develop the MGDS monitoring and control functions. This monitoring and control report provides the following information: (1) Determines the applicable requirements for a monitoring and control system for repository operations and construction (excluding Performance Confirmation). (2) Makes a determination as to whether or not … more
Date: March 31, 1998
Creator: McGrath, M.J.
Partner: UNT Libraries Government Documents Department
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PERMANENT ROCKBOLT AND TEMPORARY CHANNEL INTERACTION ANALYSIS

Description: The purpose of this analysis is to evaluate the interaction of a quality assurance (QA) classified item (QA-1 and QA-5) with an item of temporary function (QA: NONE), in accordance with Requirement 8 of the Determination of Importance Evaluation (DIE) (Reference Section 5.1). This interaction analysis will be done by determining the forces on ''Williams'' rockbolts transferred from temporary function channels under maximum capacity loads, and ensuring that these loads do not compromise the crit… more
Date: March 14, 1995
Creator: Keifer, J. & Taylor, M.
Partner: UNT Libraries Government Documents Department
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Modeling the Cathodic Region in Crevice Corrosion Under a Thin Electrolyte Film Including Particulates

Description: Crevice corrosion may be limited by the capacity of the external cathodic region to support anodic dissolution currents within the crevice. The analysis here focuses on behavior of metal surfaces covered by a thin ({approx}microns) layer of the electrolyte film including particulates. The particulates can affect the cathode current capacity (I{sub total}) by increasing the solution resistance (''volume effect'') and by decreasing the electrode area (''surface effect''). In addition, there can b… more
Date: March 14, 2006
Creator: Agarwal, A. S.; Landau, U.; Shan, X. & Payer, J. H.
Partner: UNT Libraries Government Documents Department
open access

Plutonium/High-Level Vitrified Waste Bdbe Dose Calculation

Description: In accordance with the Nuclear Waste Policy Amendments Act of 1987, Yucca Mountain was designated as the site to be investigated as a potential repository for the disposal of high-level radioactive waste. The Yucca Mountain site is an undeveloped area located on the southwestern edge of the Nevada Test Site (NTS), about 100 miles northwest of Las Vegas. The site currently lacks rail service or an existing right-of-way. If the Yucca Mountain site is found suitable for the repository, rail servic… more
Date: March 19, 2003
Creator: Richardson, D. C.
Partner: UNT Libraries Government Documents Department
open access

The Enhanced Plan for Features, Events, and Processes (FEPS) at Yucca Mountain

Description: A performance assessment is required to demonstrate compliance with the post-closure performance objectives for the Yucca Mountain Project (YMP), as stated in 10 CFR Part 63.1 13 (66 FR 55732, p. 55807). A performance assessment is defined in 10 CFR 63.2 (66 FR 55732, p. 55794) as an analysis that: (1) identifies the features, events, and processes (FEPs) that might affect the potential geologic repository; (2) examines the effects of those FEPs upon the performance of the potential geologic re… more
Date: March 25, 2002
Creator: Freeze, G.
Partner: UNT Libraries Government Documents Department
open access

Maximim Accelerations On The Fuel Assemblies Of a 21-PWR Waste Package During End Impacts

Description: The objective of this calculation is to determine the acceleration of the fuel assemblies contained in a 21-Pressurized Water Reactor (PWR) spent nuclear fuel waste package impacting an unyielding surface. A range of initial velocities of the waste package is studied. The scope of this calculation is limited to estimating the acceleration of the fuel assemblies during the impact.
Date: March 27, 2003
Creator: Brosse, V. DeLa
Partner: UNT Libraries Government Documents Department
open access

Preparing to Submit a License Application for Yucca Mountain

Description: In 1982, the U.S. Congress passed the Nuclear Waste Policy Act, a Federal law that established U.S. policy for the permanent disposal of spent nuclear fuel and high-level radioactive waste. Congress amended the Act in 1987, directing the Department of Energy to study only Yucca Mountain, Nevada as the site for a permanent geologic repository. As the law mandated, the Department evaluated Yucca Mountain to determine its suitability as the site for a permanent geologic repository. Decades of scie… more
Date: March 14, 2005
Creator: Arthur, W.J. & Voegele, M.D.
Partner: UNT Libraries Government Documents Department
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Multiscale Thermohydrologic Model Supporting the Licence Application for the Yucca Mountain Repository

Description: The MultiScale ThermoHydrologic Model (MSTHM) predicts thermal-hydrologic (TH) conditions within emplacement tunnels (drifts) and in the adjoining host rock at Yucca Mountain, Nevada, which is the proposed site for a radioactive waste repository in the US. Because these predictions are used in the performance assessment of the Yucca Mountain repository, they must address the influence of variability and uncertainty of the engineered- and natural-system parameters that significantly influence th… more
Date: March 28, 2006
Creator: Buscheck, T.A>; Sun, Y. & Hao, Y.
Partner: UNT Libraries Government Documents Department
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ROCK FALL CALCULATIONS FOR SINGLE CORROSION RESISTANT MATERIAL WASTE PACKAGES

Description: The purpose of this activity is to determine the structural performance of waste packages (WP) subject to rock fall design basis event (DBE) dynamic loads and document the calculation results that describe the threshold rock sizes for crack-initiation and through cracks in waste package shells. This activity is associated with the waste package design. AP-3.12Q, Revision 0, ICN 0, Calculations, is used to develop the calculation.
Date: March 23, 1999
Creator: Ceylan, Z.
Partner: UNT Libraries Government Documents Department
open access

IN SITU INVESTIGATION OF THE PASSIVATION OF ALLOY C22 AND OF THE PASSIVE FILMS FORMED ON ALLOY C22 IN ACIDIC ELECTROLYTES AT ROOM TEMPERATURE AND AT 90 DEGREES C

Description: The passive films formed on Alloy C22 in several acidic solutions were investigated by a combination of five in situ techniques: cyclic polarization, electrochemical impedance spectroscopy, Mott-Schottky analyses, electrochemical quartz crystal microbalance measurements, and surface enhanced Raman spectroscopy. Similar tests were conducted on unalloyed samples of nickel, chromium and molybdenum, which are the main alloying elements of Alloy C22. The results of the tests conducted on nickel, chr… more
Date: March 11, 2006
Creator: M. Miyagusuku, S. Harrington, and T. M. Devine
Partner: UNT Libraries Government Documents Department
open access

THERMAL EVALUATION OF THE CONCEPTUAL 12 PWR UNCANISTERED FUEL (UCF) TUBE BASKET DESIGN DISPOSAL CONTAINER

Description: This analysis is prepared by the Mined Geologic Disposal System (MGDS) Waste Package Development Department (WPDD) as specified in the Waste Package Implementation Plan (pp. 4-8, 4-11, 4-24, 5-1, and 5-13. Ref. 5.10) and Waste package Plan (pp. 3-15, 3-17, and 3-24, Ref. 5.9). The design data request addressed herein is: Characterize the conceptual 12 pressurized water reactor (PWR) uncanistered fuel (UCF) waste package (WP) to show that the design is feasible for use in the MGDS environment. T… more
Date: March 1, 1996
Creator: Wang, H.
Partner: UNT Libraries Government Documents Department
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NORTH PORTAL - DOMESTIC COLD WATER CALCULATION - CHANGE HOUSE FACILITY #5008

Description: The purpose of this design analysis and calculation is to determine the demand for domestic cold water and to size the supply main piping for the Change House Facility No.5008 in accordance with the Uniform Plumbing Code (Section 4.4.1) and US Department of Energy Order 6430.1A-1540 (Section 4.4.2).
Date: March 2, 2000
Creator: Mastilovic, S.
Partner: UNT Libraries Government Documents Department
open access

Natural Analoges as a Check of Predicted Drift Stability at Yucca Mountain, Nevada

Description: Calculations made by the U.S. Department of Energy's Yucca Mountain Project as part of the licensing of a proposed geologic repository (in southwestern Nevada) for the disposal of high-level radioactive waste, predict that emplacement tunnels will remain open with little collapse long after ground support has disintegrated. This conclusion includes the effects of anticipated seismic events. Natural analogues cannot provide a quantitative test of this conclusion, but they can provide a reasonabl… more
Date: March 10, 2006
Creator: Stuckless, J.
Partner: UNT Libraries Government Documents Department
open access

Uranium and Neptunium Desorption from Yucca Mountain Alluvium

Description: Uranium and neptunium were used as reactive tracers in long-term laboratory desorption studies using saturated alluvium collected from south of Yucca Mountain, Nevada. The objective of these long-term experiments is to make detailed observations of the desorption behavior of uranium and neptunium to provide Yucca Mountain with technical bases for a more realistic and potentially less conservative approach to predicting the transport of adsorbing radionuclides in the saturated alluvium. This pap… more
Date: March 16, 2006
Creator: Scism, C. D.; Reimus, P. W.; Ding, M. & Chipera, S. J.
Partner: UNT Libraries Government Documents Department
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Compositional and Structural Control on Anion Sorption Capability of Layered Double Hydroxides (LDHS)

Description: Layered double hydroxides (LDHs) have shown great promise as anion getters. In this paper, we demonstrate that the sorption capability of a LDH for a specific oxyanion can be greatly increased by appropriately manipulating material composition and structure. A large set of LDH materials have been synthesized with various combinations of metal cations, interlayer anions, and the molar ratios of divalent cation M(II) to trivalent cation M(III). The synthesized materials have then been tested syst… more
Date: March 16, 2006
Creator: Wang, Y. & Gao, H.
Partner: UNT Libraries Government Documents Department
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Sensitivity Analysis of Hydrological Parameters in Modeling Flow and Transport in the Unsaturated Zone of Yucca Mountain

Description: The unsaturated fractured volcanic deposits at Yucca Mountain have been intensively investigated as a possible repository site for storing high-level radioactive waste. Field studies at the site have revealed that there exist large variabilities in hydrological parameters over the spatial domain of the mountain. This paper reports on a systematic analysis of hydrological parameters using the site-scale 3-D unsaturated zone (UZ) flow model. The objectives of the sensitivity analyses are to evalu… more
Date: March 21, 2006
Creator: Zhang, K.; Wu, Y.S. & Houseworth, J.E.
Partner: UNT Libraries Government Documents Department
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Radionuclide Inventories for DOE SNF Waste Stream and Uranium/Thorium Carbide Fuels

Description: The objective of this calculation is to generate radionuclide inventories for the Department of Energy (DOE) spent nuclear fuel (SNF) waste stream destined for disposal at the potential repository at Yucca Mountain. The scope of this calculation is limited to the calculation of two radionuclide inventories; one for all uranium/thorium carbide fuels in the waste stream and one for the entire waste stream. These inventories will provide input in future screening calculations to be performed by Pe… more
Date: March 28, 2000
Creator: Goluoglu, K.L.
Partner: UNT Libraries Government Documents Department
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