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Reaction of Topopah Spring tuff with J-13 water at 150{sup 0}C: samples from drill cores USW G-1, USW GU-3, USW G-4, and UE-25h No. 1

Description: Samples of Topopah Spring tuff selected from vertical drill holes USW G-1, GU-3, and G-4, and from the horizontal air-drilled hole at Fran Ridge were reacted with J-13 water at 150{sup 0}C. The primary purpose of these experiments was to compare the resulting solution chemistries to estimate the degree of homogeneity that might be expected in thermally affected ground water in a potential nuclear waste repository at Yucca Mountain. The second purpose was to relate data obtained from welded devi… more
Date: March 3, 1985
Creator: Oversby, V.M.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Colloid transport code-nuclear user`s manual

Description: This report describes the CTCN computer code, designed to solve the equations of transient colloidal transport of radionuclides in porous and fractured media. This Fortran 77 package solves systems of coupled nonlinear differential equations with a wide range of boundary conditions. The package uses the Method of Lines technique with a special section which forms finite-difference discretizations in up to four spatial dimensions to automatically convert the system into a set of ordinary differe… more
Date: April 3, 1992
Creator: Jain, R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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REQUIREMENTS ALLOCATION ANALYSIS FOR NORTH RAMP EXCAVATION AND LAYOUT, CII: BABEAD000

Description: The purpose and objective of this analysis is to allocate all Exploratory Studies Facility Design Requirements (ESFDR) (Reference 8.1) applicable to Configuration Item (CI) North Ramp Excavation and Layout, Configuration Item Identifier (CII) BABEAD000.
Date: January 3, 1995
Creator: Kennedy, W. R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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IDCS NETWORK ALTERNATIVES ANALYSIS

Description: The purpose of this design analysis is to determine the feasibility of network alternatives available to support the Exploratory Study Facilities (ESF) site characterization test data gathering activity as well as the facility control and monitoring systems. If it is found that more than one feasible alternative exists, a cost analysis will also be conducted to determine the least costly alternative.
Date: February 3, 1995
Creator: Rosche, R.T.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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IDCS NETWORK AND STORAGE DATA RATE ANALYSIS

Description: The purpose of this design analysis is to establish estimated data rates for the Integrated Data and Control System (IDCS). These estimated data rates will be used to determine network traffic rates and data storage requirements for the initial IDCS installation as well as the longer term requirements. The data rates presented herein are largely based upon assumptions and therefore require close scrutiny from reviewers. It cannot be overemphasized that small changes in assumptions can lead to s… more
Date: February 3, 1995
Creator: Rosche, R.T.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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[Paleoclimatology studies for Yucca Mountain site characterization]. Final report

Description: This report consists of two separate papers: Fernley Basin studies; and Influence of sediment supply and climate change on late Quaternary eolian accumulation patterns in the Mojave Desert. The first study involved geologic mapping of late Quaternary sediments and lacustrine features combined with precise control of elevations and descriptions of sediments for each of the major sedimentary units. The second paper documents the response of a major eolian sediment transport system in the east-cen… more
Date: May 3, 1996
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Nuclear waste criticality analysis. Final report, 1 July 1995--30 June 1996

Description: The natural reactors that occurred in Gabon, Africa over 2 billion years ago present an interesting analog to the underground repositories proposed around the world for the long-term storage of high-level spent nuclear fuel. Many articles have been written concerning the low migration rates of actinides and fission products from the Oklo reactor sites, but Oklo also presents researchers with an opportunity to discover the conditions that led to nuclear criticality in uranium oxides with low enr… more
Date: July 3, 1996
Creator: Culbreth, W.G.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Repository seals requirement study

Description: The Yucca Mountain Site Characterization Project, managed by the Civilian Radioactive Waste Management System (CRWMS) Management and Operating Contractor (M and O) is conducting investigations to support the Viability Assessment and the License Application for a high-level nuclear waste repository at Yucca Mountain, Nevada. The sealing subsystem is part of the Yucca Mountain Waste Isolation System. The Yucca Mountain Site Characterization Project is currently evaluating the role of the sealing … more
Date: November 3, 1997
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Repository seals requirements study

Description: The Yucca Mountain Site Characterization Project, managed by the Civilian Radioactive Waste Management System (CRWMS) Management and Operating Contractor (M and O) is conducting investigations to support the Viability Assessment and the License Application for a high-level nuclear waste repository at Yucca Mountain, Nevada. The sealing subsystem is part of the Yucca Mountain Waste Isolation System. The Yucca Mountain Site Characterization Project is currently evaluating the role of the sealing … more
Date: November 3, 1997
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Preliminary description of small block mineralogical features, data report

Description: The large block heater test, to be conducted at Fran Ridge (Lin et al., 1994), is designed to provide a database with which to test codes that simulate hydrological, geochemical, and geomechanical processes that may occur within the repository block. The geochemical processes that may occur include rock-water interaction within the matrix of fracture bounded blocks, and with the minerals that line fractures (see, for example, Buscheck and Nitao, 1992,1993ab, 1994; Glassley, 1993). As a first st… more
Date: February 3, 1998
Creator: Glassley, W., LLNL
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Review of existing reactive transport software

Description: Simulations of thermal and hydrological evolution following the potential emplacement of a subterranean nuclear waste repository at Yucca Mountain, NV provide data that suggest the inevitability of dependent, simultaneous chemical evolution in this system. These chemical changes will modify significantly both the magnitude and structure of local porosity and permeability; hence, they will have a dynamic feedback effect on the evolving thermal and hydrological regime. Yet, despite this intimate … more
Date: February 3, 1998
Creator: Glassley, W., LLNL
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Biochemical Contributions to Corrosion of Carbon Steel and Alloy 22 in a Continual Flow System

Description: Microbiologically influenced corrosion (MIC) may decrease the functional lifetime of nuclear waste packaging materials in the potential geologic repository at Yucca Mountain (YM), Nevada. Biochemical contributions to corrosion of package materials are being determined in reactors containing crushed repository-site rock with the endogenous microbial community, and candidate waste package materials. These systems are being continually supplied with simulated ground water. Periodically, bulk chemi… more
Date: December 3, 1998
Creator: Horn, J.; Martin, S.; Masterson, B. & Lian, T.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Data Qulaification Report Flowong Interval Data for Use On the Yucca Mountain Project

Description: This data qualification report uses technical assessment and corroborating data methods according to Attachment 2 of AP-SIII.2Q, Rev. 0, ICN 2, ''Qualification of Unqualified Data and the Documentation of Rationale for Accepted Data'', to qualify flowing interval data. This report was prepared in accordance with Data Qualification Plan TDP-NBS-GS-000035, Revision 1. Flowing interval location data from borehole tracejector surveys and fracture dip data from acoustic televiewer logging are evalua… more
Date: August 3, 2000
Creator: Wilson, C.R. & Grant, T.A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Design Verification Report Spent Nuclear Fuel (SNF) Project Canister Storage Building (CSB)

Description: The Sub-project W379, ''Spent Nuclear Fuel Canister Storage Building (CSB),'' was established as part of the Spent Nuclear Fuel (SNF) Project. The primary mission of the CSB is to safely store spent nuclear fuel removed from the K Basins in dry storage until such time that it can be transferred to the national geological repository at Yucca Mountain Nevada. This sub-project was initiated in late 1994 by a series of studies and conceptual designs. These studies determined that the partially cons… more
Date: November 3, 2000
Creator: BAZINET, G.D.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Inventory Abstraction

Description: The purpose of the inventory abstraction as directed by the development plan (CRWMS M&O 1999b) is to: (1) Interpret the results of a series of relative dose calculations (CRWMS M&O 1999c, 1999d). (2) Recommend, including a basis thereof, a set of radionuclides that should be modeled in the Total System Performance Assessment in Support of the Site Recommendation (TSPA-SR) and the Total System Performance Assessment in Support of the Final Environmental Impact Statement (TSPA-FEIS). (3) … more
Date: November 3, 2000
Creator: Leigh, C.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Vapor-Phase Garnet at Yucca Mountain, Nevada: Geochemistry and Oxygen-Isotope Thermometry

Description: About 20 vapor-phase garnets were studied in two samples of the Topopah Spring Tuff from Yucca Mountain, in southern Nevada. The Miocene-age Topopah Spring Tuff is a 350-m-thick, devitrified, moderately to densely welded ash flow that is compositionally zoned from high-silica rhyolite to quartz latite. During cooling of the tuff, escaping vapor produced lithophysae (former gas cavities) lined with an assemblage of tridymite, cristobalite, alkali feldspar, and locally, hematite and/or garnet. Va… more
Date: July 3, 2001
Creator: Moscati, R. J.; Johnson, C. A. & Whelan, J. F.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Measuring and Modeling Flow in Welded Fractured Tuffs

Description: We have carried out a series of in situ liquid-release experiments in conjunction with a numerical modeling study to examine the effect of the rock matrix on liquid flow and transport occurring primarily through the fracture network. Field experiments were conducted in the highly fractured Topopah Spring welded tuff at a site accessed from the Exploratory Studies Facility (ESFS), an underground laboratory in the unsaturated zone at Yucca Mountain, Nevada. During the experiment, wetting-front mo… more
Date: October 3, 2001
Creator: Salve, R.; Doughty, C. & Wang, J.S.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Evaluation of the Thermal Response of the 5-DHLWaste Package-Hypothetical Fire Accident

Description: The purpose of this calculation is to determine the thermal response of the 5-defense high level waste (DHLW)/Department of Energy (DOE) codisposal waste package (WP) to the hypothetical fire accident. The objective is to calculate the temperature response of the DHLW glass to the hypothetical short-term fire defined in 10 CFR 71, Section 73(c)(4), Reference 1. The scope of the calculation includes evaluation of the accident with the waste package above ground, at the Yucca Mountain surface fac… more
Date: November 3, 2001
Creator: Moore, R.W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

ECRB REFUGE CHAMBER

Description: The purpose of this calculation is to identify the initial design requirements for refuge stations, including the client requirements, standards, codes, laws, and regulations, general discipline design criteria, and design basis events and hazards. The scope of this document is for the specific task of designing and constructing refuge stations in the Enhanced Characterization Repository Block (ECRB) subsurface openings as necessary personnel safety enhancements to the current construction, mai… more
Date: December 3, 2001
Creator: Keifer, J. W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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