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in publisher: "United States. Department of Energy. Yucca Mountain Project Office."  
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Osmotic Coefficients, Solubilities, and Deliquescence Relations in Mixed Aqueous Salt Solutions at Elevated Temperature

Description: While thermodynamic properties of pure aqueous electrolytes are relatively well known at ambient temperature, there are far fewer data for binary systems extending to elevated temperatures and high concentrations. There is no general theoretically sound basis for prediction of the temperature dependence of ionic activities, and consequently temperature extrapolations based on ambient temperature data and empirical equations are uncertain and require empirical verification. Thermodynamic propert… more
Date: February 22, 2006
Creator: Gruszkiewicz, M. S. & Palmer, D. A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Performance Assessment of Disposal of Selected U.S. Department of Energy Spent Fuel in High Integrity Cans

Description: The purpose of this calculation is to determine the effects on long-term dose from disposing of selected U. S. Department of Energy (DOE) spent nuclear fuel (DSNF) in high integrity cans (HICs). The Civilian Radioactive Waste Management System Management and Operating contractor (CRWMS M&O) prepared the calculation as part of Performance Assessment (PA) activities for the DOE Yucca Mountain Project. DSNF encompasses approximately 2,500 MTHM (metric tons heavy metal) consisting of over 200 f… more
Date: December 22, 2000
Creator: Saulnier, G. J., Jr.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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A Science-Based Approach to Understanding Waste Form Durability in Open and Closed Nuclear Fuel Cycles

Description: There are two compelling reasons for understanding source term and near-field processes in a radioactive waste geologic repository. First, almost all of the radioactivity is initially in the waste form, mainly in the spent nuclear fuel (SNF) or nuclear waste glass. Second, over long periods, after the engineered barriers are degraded, the waste form is a primary control on the release of radioactivity. Thus, it is essential to know the physical and chemical state of the waste form after hundred… more
Date: June 22, 2006
Creator: Peters, M. T. & Ewing, R. C.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Preliminary Transportation, Aging and Disposal Canister System Performance Specification

Description: This document provides specifications for selected system components of the Transportation, Aging and Disposal (TAD) canister-based system. A list of system specified components and ancillary components are included in Section 1.2. The TAD canister, in conjunction with specialized overpacks will accomplish a number of functions in the management and disposal of spent nuclear fuel. Some of these functions will be accomplished at purchaser sites where commercial spent nuclear fuel (CSNF) is store… more
Date: November 22, 2006
Creator: Kouts, C.A
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Environment on the Surfaces of the Drip Shield and Waste Package Outer Barrier

Description: This report provides supporting analysis of the conditions at which an aqueous solution can exist on the drip shield or waste package surfaces, including theoretical underpinning for the evolution of concentrated brines that could form by deliquescence or evaporation, and evaluation of the effects of acid-gas generation on brine composition. This analysis does not directly feed the total system performance assessment for the license application (TSPA-LA), but supports modeling and abstraction o… more
Date: February 22, 2005
Creator: Wolery, T.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Probability Distribution for Flowing Interval Spacing

Description: Fracture spacing is a key hydrologic parameter in analyses of matrix diffusion. Although the individual fractures that transmit flow in the saturated zone (SZ) cannot be identified directly, it is possible to determine the fractured zones that transmit flow from flow meter survey observations. The fractured zones that transmit flow as identified through borehole flow meter surveys have been defined in this report as flowing intervals. The flowing interval spacing is measured between the midpoin… more
Date: September 22, 2004
Creator: Kuzio, S.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Drift-Scale Radionuclide Transport

Description: The purpose of this model report is to document the drift scale radionuclide transport model, taking into account the effects of emplacement drifts on flow and transport in the vicinity of the drift, which are not captured in the mountain-scale unsaturated zone (UZ) flow and transport models ''UZ Flow Models and Submodels'' (BSC 2004 [DIRS 169861]), ''Radionuclide Transport Models Under Ambient Conditions'' (BSC 2004 [DIRS 164500]), and ''Particle Tracking Model and Abstraction of Transport Pro… more
Date: September 22, 2004
Creator: Houseworth, J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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FUEL HANDLING FACILITY BACKUP CENTRAL COMMUNICATIONS ROOM SPACE REQUIREMENTS CALCULATION

Description: The purpose of the Fuel Handling Facility Backup Central Communications Room Space Requirements Calculation is to determine a preliminary estimate of the space required to house the backup central communications room in the Fuel Handling Facility (FHF). This room provides backup communications capability to the primary communication systems located in the Central Control Center Facility. This calculation will help guide FHF designers in allocating adequate space for communications system equipm… more
Date: March 22, 2005
Creator: SZALEWSKI, B.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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SEEPAGE MODEL FOR PA INCLUDING DRIFT COLLAPSE

Description: The purpose of this report is to document the predictions and analyses performed using the seepage model for performance assessment (SMPA) for both the Topopah Spring middle nonlithophysal (Tptpmn) and lower lithophysal (Tptpll) lithostratigraphic units at Yucca Mountain, Nevada. Look-up tables of seepage flow rates into a drift (and their uncertainty) are generated by performing numerical simulations with the seepage model for many combinations of the three most important seepage-relevant para… more
Date: September 22, 2004
Creator: Tsang, C.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

ELECTRICAL POWER SYSTEM DESCRIPTION DOCUMENT

Description: The purpose of this revision of the System Description Document (SDD) is to establish requirements that drive the design of the electrical power system and their bases to allow the design effort to proceed to License Application. This SDD is a living document that will be revised at strategic points as the design matures over time. This SDD identifies the requirements and describes the system design as they exist at this time, with emphasis on those attributes of the design provided to meet the… more
Date: June 22, 2004
Creator: Maniyar, M.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Initial Cladding Condition

Description: The purpose of this analysis is to describe the condition of commercial Zircaloy clad fuel as it is received at the Yucca Mountain Project (YMP) site. Most commercial nuclear fuel is encased in Zircaloy cladding. This analysis is developed to describe cladding degradation from the expected failure modes. This includes reactor operation impacts including incipient failures, potential degradation after reactor operation during spent fuel storage in pool and dry storage and impacts due to transpor… more
Date: August 22, 2000
Creator: Siegmann, E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Determination of Importance Evaluation for Exploratory Studies Facility (ESF) Subsurface Testing Activities

Description: This Determination of Importance Evaluation (DIE) applies to the Subsurface Exploratory Studies Facility (ESF), encompassing the Topopah Spring (TS) Loop from Station 0+00 meters (m) at the North Portal to breakthrough at the South Portal (approximately 78+77 m), and ancillary test and operation support areas including the Enhanced Characterization of the Repository Block (ECRB) Cross Drift. This evaluation applies specifically to site characterization testing activities ongoing and planned in … more
Date: July 22, 2002
Creator: Goodin, S.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Modeling Transport in Fractured Porous Media with the Random-Walk Particle Method: The Transient Activity Range and the Particle-Transfer Probability

Description: Multiscale features of transport processes in fractured porous media make numerical modeling a difficult task, both in conceptualization and computation. Modeling the mass transfer through the fracture-matrix interface is one of the critical issues in the simulation of transport in a fractured porous medium. Because conventional dual-continuum-based numerical methods are unable to capture the transient features of the diffusion depth into the matrix (unless they assume a passive matrix medium),… more
Date: October 22, 2001
Creator: Pan, Lehua & Bodvarsson, G.S.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

YMP Engineered Barrier Systems Scaled Ventilation Testing

Description: Yucca Mountain, approximately 100 miles northwest of Las Vegas, Nevada, has been selected as the site for the nation's first geologic repository for high level nuclear waste. The Yucca Mountain Project (YMP) is currently developing the design for the underground facilities. Ventilation is a key component of the design as a way to maintain the desired thermal conditions in the emplacement drifts prior to closure. As a means of determining the effects of continuous ventilation on heat removal fro… more
Date: November 22, 2002
Creator: Dunn, S.D.; Lowry, B.; Walsh, B.; Mar, J.D.; Howard, C.; Johnston, R. et al.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

On the Existence of Our Metals-Based Civilization: I. Phase Space Analysis

Description: The stability of the barrier layers of bilayer passive films that form on metal and alloy surfaces, when in contact with oxidizing aqueous environments, is explored within the framework of the Point Defect Model (PDM) using phase-space analysis (PSA), in which the rate of growth of the barrier layer into the metal, (dL{sup +}/dt), and the barrier layer dissolution rate, (dL{sup -}/dt), are plotted simultaneously against the barrier layer thickness. A point of intersection of dL{sup -}/dt with d… more
Date: June 22, 2005
Creator: Macdonald, D.D.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

2003 International High-Level Radioactive Waste Management Conference Breached Drip Shield Test and Validation of a TSPA Sub-Model

Description: The Engineered Barrier System (EBS) represents the system of human engineered barriers in the isolation of high-level radioactive waste in the proposed repository at Yucca Mountain. It is designed to complement and enhance the natural barriers to isolate and prevent the transport of radionuclides into the surrounding environment. The transport mechanism most frequently postulated for radionuclides is liquid water flux that has penetrated the EBS through corrosion breaches in the drip shield and… more
Date: November 22, 2002
Creator: Walton, Z.P. & Kam, J.T.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Automatic Software Processing for Inventories of Nuclides (ASPIN)

Description: EQ6 users have difficulties tracking isotopic concentrations in a system with chemical and nuclear decay reactions. The capability to track isotopic concentrations is particularly important for simulating the degradation of the spent nuclear fuels. Isotopic tracking is necessary to evaluate the criticality risk associated with fissile material relocation inside of a disposal container. A code called ASPRIN (Automatic Software PRocessing, Inventories of Nuclides) was created to allow isotopic tr… more
Date: October 22, 2001
Creator: Gratton, Luca & Rammsy, J. M.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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