CIVIL ENGINEERING DATABASE
AMERICAN SOCIETY OF CIVIL ENGINEERS
ASCE LIBRARY
All Proceeding Papers /Chapters
Stresses in Faulted Tunnel Models by Photoelasticity and Adaptive Finite Element
Evolving Fracture Arrays and Associated Changes in Rock Mass Properties
Anisotropy of Mechanical Properties of Tuff at Yucca Mountain
Thermal Stress in Backfilled Circular Tunnel Due to 21 PWR MPC's
Micro-Scale Studies of Unsaturated Flow in Fractured Media
Assessing Alternative Conceptual Models of Fracture Flow
Experimental and Numerical Aqueous Flow Through a Partially Saturated Fracture
On Water Infiltration in Rough-Walled Fractures
A Simple Procedure for Estimating the Effective Conductivity of a Two-Dimensional Saturated or Partly-Saturated Fracture Network
The Projekt of an Underground Bureal of Radioactive Waste of Mean and Low Activity for the Central Region of the Russia
Principal Aspects of Petrographical Examination of Rock Salts to Assess Their Suitability for Radioactive Waste Disposal
Deformation of Underground Deep Cavities in Rock Salts at Their Long-Term Operations
Geological Suitability Studies as to Burial of Radioactive Waste in Salts and Tuffs of the Transcarpathian Depression
Effective Media Models for Unsaturated Fractured Rock: A Field Experiment
Fracture Permeability Under Effect of Normal and Shear Stress: A Preliminary Experimental Investigation
Permeability of Fractured Tuff as Functions of Temperature and Confining Pressure
The Large Block Test, A Progress Report
Measuring Geomechanical Properties of Topopah Spring Tuff at the 1-Meter Scale
Ventilation and Vapor-Phase Transport Near the ESF Tunnel
Effect of Environmental Variables on CO<sub>2</sub> Transport Through USW-G4 Tuffs
A Capillary Network Model for Gas Migration in Engineered Barriers
Gasgeodynamical Method for the Assessment of Rock Massif for Raw Disposal
Spatial Resolution in Hydrologic Characterization
Numerical and Physical Testing of Upscaling Techniques for Constitutive Properties
Estimation of Spatial Distribution of Recharge Factors at Yucca Mountain, Nevada
Characterization of the Potential for Perched Water Development at Yucca Mountain, Nevada
Proof-of-principle Tests of the REKA Method for the In Situ Thermophysical Property Measurement
Calculation of Thermal Conductivity of Unsaturated Porous Media Based on Microscopic Fluid Distribution
Modeling Spatial Heterogeneity of Thermal Conductivity Using a Surrogate Property
Simflied Thermomechanical Models for Analysis of Deep Clay Repositories
Radionuclide Migration Experiments Under In Situ Conditions
Reactive Transport Studies at the Raymond Field Site
The Role of Cation Exchange in Controlling Groundwater Chemistry at ?sp?, Sweden
Calcite Fracture Fillings as Indicators of Paleohydrology at the ?sp? Hard Rock Laboratory, Sweden
Calcite and Zeolite Fracture Coatings in Topopah Spring Tuff Along Drill Hole Wash, Yucca Mountain, Nevada
Potential Fast Paths Along Faults in the Calico Hills Unit at Yucca Mountain
Particle Tracking for Unsaturated-Zone Groundwater Travel Time Analysis at Yucca Mountain
Radiocolloid Migration Through Backfill-Surrounding Porous Media in Semi-Infinite Cylindrical Geometry
An Integrated System for Groundwater Monitoring at Sellafield PNWR, U.K.
A Preliminary Three-Dimensional Geological Framework Model for Yucca Mountain
Evaluation of Uncertainty in Geological Framework Models at Yucca Mountain, Nevada
Geophysical Expression of the Ghost Dance Fault, Yucca Mountain, Nevada
Discrete Fracture Modeling-ESF North Portal Area, Yucca Mountain Nevada
Depth to Pre-Cenozoic Basement in Southwest Nevada
Amphibole in Quaternary Basalts of the Yucca Mountain Region: Significance to Volcanism Models
Eolian-Deposited Minerals Around Drill Hole USW SD-9, Yucca Mountain, Nevada
Neptunium, Plutonium, and Americium Solubility and Speciation Studies in a Neutral Electrolyte with a Total Carbonate Concentration Simulating UE-25P#1 Well Water
Selection of Geological Formations for Low- and Intermediate Level Radioactive Waste Disposal in Hungary
Radioactive Waste Management in Poland Status and Strategy for the Future
Hydrogeological Conditions of Preselected Sites for Raw Disposal in Geological Formations of Ukraine
Evaluation of Geological Formations of Eastern Europe Countries for Raw Disposal and Elaboration of Joint R&D Programmes
A Project of Classification of Large Geologic Structures of the Earth's Crust According to the Conditions of Radioactive Waste Disposal
Inverse Modeling as a Step in the Calibration of the LBL-USGS Site-Scale Model of Yucca Mountain
Recent Development of the LBL/USGS Site-Scale Model of Yucca Mountain, Nevada
Flow and Transport Simulation in Yucca Mountain Using Dual-Porosity Model
Air-Tough: A Fully 3-Dimensional Linking of Atmosphere with Soil Using Eddy Diffusivity Concept and V-Tough
Contaminated Groundwater Transport Using an Adaptive 3-D Finite Element Model
Underground Laboratories - A Site Characterization Tool for Nuclear Fuel Waste Disposal in Canada
Contributions of the Grimsel Test Site (GTS) To Swiss Site Characterisation Programmes
The R?le of the ?sp? Hard Rock Laboratory in the Swedish Deep Repository Programme
Underground Test Program for the Yucca Mountain, Nevada Potential High-Level Waste Repository Site
Defining Modeling Parameters for Juniper Trees Assuming Pleistocene-Like Conditions at the NTS
Radiocarbon Dating of Fossil Mollusk Shells in the Yucca Mountain Region
Defining Limitations for Use of the Help Model
Parametric Analysis of a 1-D Infiltration Model for Yucca Mountain
Effects of Alluvial Depth on long-Term Infiltration at Yucca Mountain, NV
The Role of the Rock Characterisation Facility in the Nirex Programme to Evaluate the Suitability of the Sellafield Site for Disposal of Intermediate Level Waste
Current Situation and Perspective for Using Underground Laboratories in the Spanish HLW Program
Implementation of the Underground Tests at the Exploratory Studies Facility
Zedex - An In-Situ Study of the Importance of the Excavation Disturbed Zone to Repository Performance
Compartmentalized Saturated Flow at Yucca Mountain
Two-Phase Flow in Regionally Saturated Fractured Rock Near Excavations
Near Drift Two-Phase Flow Processes Within Regionally Saturated Fractured Rock
A Cellular Automaton Simulation of Contaminant Transport in Porous Media
Approach to Calculation of Pre-Waste-Emplacement Ground-Water Travel Time
Unsaturated-Zone Fast-Path Flow Calculations for Yucca Mountain GWTT Analyses
Preliminary Sensitivity Studies of Fast-Path Flow on a Cross-Section of Yucca Mountain, Nevada
Numerical Analysis of a Proposed Percolation Experiment at The Pe?a Blanca Natural Analog Site
The Role of Ground-Water Travel Time in Suitability and Licensing
Adsorption Study for Uranium in Rocky Flats Groundwater
Uniform Surface Complexation Approaches to Radionuclide Sorption Modeling
Paleohydrological Mixing Portions in One Deep Borehole at The Swedish ?sp? Hard Rock Laboratory
Groundwater Predictions in the Swedish ?sp? Hard Rock Laboratory
Recent Developments in Sweden on Spent Fuel Management
Tailored Model Abstraction in Performance Assessments
Abstraction of Information in Repository Performance Assessments. Examples From the Ski Project Site-94
Approaches to Model Abstraction for Performance Assessment
Development of a System Model for the Postclosure Assessment of a Concept for Geological Disposal of Canada's Nuclear Fuel Waste
Testing the Abstractions Used in Total System Performance Assessments
On the Estimation of Bias in Post-Closure Performance Assessment of Underground Radioactive Waste Disposal
Preparing Scientists and Engineers to Interact with NRC
Understanding How to Maintain Compliance in the Current Regulatory Climate
Regulatory Issues Associated with the Multi-Purpose Canister System
A Current Evaluation of LSS Requirements and Implementation
The Many Barriers of Yucca Mountain
The Need to Address Enhanced Radon Emission in the Environmental Impact Report of Yucca Mountain
Future Water Table Rise at Yucca Mountain: A Regulatory Perspective
Experimental Investigation of Natural Convection About Drift-Emplaced Waste Canisters
Thermo-Hydro-Mechanical Modelling of an Underground Radioactive Wastes Disposal in Clayey Formation
Transport Processes in Unsaturated Soils at Sub-Residual Saturations
Improved Accuracy of Thermal Source Terms for Thermal Load Predictions
Notice of Inquiry on Waste Acceptance Issues: Summary of Responses and Comments
Development of a Safeguards and Security Program for the Civilian Radioactive Waste Management Program
Long Term Maintenance of Records and Documents for Radioactive Waste Repositories
System Impacts of Fuel Selection and MPC Heat Limits
Effect of Areal Power Density and Relative Humidity on Corrosion Resistant Container Performance
Hydrothermal Analyses at the Waste-Package Scale for a Potential High-Level Waste Repository at Yucca Mountain
Preliminary Evaluation of Waste Package Releases Using Drift-Scale Thermo-Hydrologic Analyses
Analaysis of Near-Field Thermal and Psychometric Waste Package Environment Using Ventilation
TOUGH2 Model of the G-Tunnel Heater Test
Systems Engineering Overview at the Waste Acceptance, Storage, and Transportation Project
Projections for Spent Nuclear Fuel Accumulations in Dry Storage at Reactor Sites for A Range of Operating Scenarios
Life-Cycle Cost Implications of a System Using Bare SNF Transfer
Impacts of the Use of Spent Nuclear Fuel Burnup Credit on DOE Advanced Technology Legal Weight Truck Cask GA-4 Fleet Size
Feasibility of Cooling Emplacement Drifts by Ventilation Air and Effects of Pre-Cooling Intake Air by Refrigeration
Unsaturated Flows in a Porous Medium Containing a Heated Air Annulus
Use of Geostatistical Modeling to Capture Complex Geology in Finite-Element Analysis
Drift Scale Thermomechanical Analysis for Thermal Loading and Retrievability Studies
Site Suitability Evaluation Process Development, The Situs Jurisdiction's Perspective
Mined Geologic Disposal System Concept of Operations
King, John F.
Application of Systems Engineering Techniques in NRC's High-Level Waste Regulatory Program
Impacts of MPC Thermal Limits on Cooling Storage Requirements at the Repository
Radon Concentration and Working Level in the Exploratory Studies Facility (ESF)
Preclosure Radiological Safety Assessment for the Ground Support System in the Exploratory Studies Facility
Effects of Exploratory Studies Facility Construction Water on Radionuclide Release
Continuous, Environmental Radon Monitoring Program at The Yucca Mountain Site Characterization Project
Coupling Between Water Chemistry and Thermal Output at Unsaturated Repositories
The Development and Usage of New Chemical Transport Code: Arest-CT
Comparison of EPRI and Sandia Performance Assessment Assumptions
Recent Progress in Scenario Development for the WIPP
Recent Scenario Development Methodologies Within SKB
Preliminary Evaluation of Predicted Peak Release Rates from the Engineered Barrier System for a Potential Repository at Yucca Mountain, Nevada
The Development of a Private, Centralized Spent Fuel Storage Facility
Dry Spent Fuel Transfer System Design
MPC System Development a Utility Industry Assessment
Integrated Waste Management System Costs in a MPC System
Bowser, Rita C.
Use of Modeling in Repository Licensing
A Regulatory Perspective on Model Validation
Approach to Compliance with the NRC Substantially Complete Containment Requirement at the Potential Repository at Yucca Mountain
Proposed WIPP Compliance Criteria (40 CFR Part 194)
Disposition of Excess Plutonium - Overview
Disposition of Two Plutonium Waste Forms in a Geologic Repository Regulatory/Statutory Issues and Impacts
Characteristics of Spent Mox Fuel Resulting From Disposition of SFM and Potential Impacts on the CRWMS
Comparative Repository Performance of Plutonium Forms - Initial Studies
Role of Performance Assessments in the SKB Siting
The Ski Repository Performance Assessment Project Site-94
Implications of Colloids on the Performance of a HLW Repository
Proposed Models of Colloid-Facilitated Transport for Total-System Performance Assessment
Outstanding Issues for Transuranic Waste Disposal at WIPP
The Foundations of the HMIP System Simulation Approach to Performance Assessment
An Analytical Hierarchy Process for Decision Making of High-Level-Waste Management
Software for Automated Tracking of Open Items at NRC
Expert Judgment in NRC Licensing Proceedings and Its Impact on the Regulatory Decision-Making Process
Assessing Volcanic Hazard at Yucca Mountain Using Expert Judgment
Lessons Learned From the Shoreham Fuel Shipping Experience
Human Factors Data Collection and Analysis for Operational Evaluation and Performance Assessment
A Review of Accident Response Models for Risk Assessments Involving the Transport of Spent Nuclear Fuel
Development of the OCRWM Transportation Geographic Information System
Packaging and Transportaton Issues Associated with Meeting the Spent Fuel Standard
On Significance of Route Specific Data for Transportation Risk Analysis
Design of a Transportation Impact Analysis System
Natural Elemental Fluxes as Licensing Criteria: A Methodology
The Development of a Methodology for Biosphere Analysis Within the Framework of Performance Assessment
A Simple Model for Determining Radionuclide Release and Migration to the Biosphere
Unsaturated Zone Transport Modeling of the Greater Confinement Disposal Site
SSI Toolbox to Evaluate Swedish High-Level Waste Disposal System Performance
Yankee Approach to Disposal of Greater-Than-Class C (GTCC) Waste
Canisters and Nonfuel Components at Commercial Nuclear Reactors
Non-Fuel Assembly Components: 10 CFR 61.55 Classification for Waste Disposal Using ORIGEN2
Single Waste Form Repository: Conversion of Miscellaneous Wastes to Glass
Re-Engineering Quality Related Processes and Activities
Utilizing Today's Technology to Improve the Procedure Development Process
Software QA for the Yucca Mountain Project
Technical Data Hierarchy and Control at the Yucca Mountain Project
Project and Process Effectiveness Using Performance-Based Auditing Techniques
Durability Testing of the High-Capacity GA-4/GA-9 Trailer
GA-4 Half-Scale Cask Model Fabrication
Interim Storage Cask Design
Assessment of the Performance of the SMERF Indoor Fire Facility with the Use of an Active Calorimeter
Transportation Package Thermal and Shielding Response to a Regulatory Fire
Update on the PWR Axial Burnup Profile Database
Reactivity Effects of Nonuniform Axial Burnup Distributions on Spent Fuel
Long-Term Criticality Analyses Process
Dry Fuel Storage Cask Shielding Benchmarks
ARP: A PC-Compatible Scheme for Generating Origen-S Cross Section Library
Burnup Verification at Arkansas Nuclear One-Unit 1 Using the Fork Measurement System
Archaeological and Industrial Analogues for Deep Repository Materials
Integrated Corrosion Facility for Long-Term Testing of Candidate Materials for High-Level Radioactive Waste Containment
A Corrosion Model For Waste Package Corrosion-Allowance Materials
Performance Assessment Modeling of High Level Nuclear Waste Containers
Synthesis of 1.1 NM Tobermorite: A Cement Phase Expected Under Repository Conditions
Correlation of Drop Test Results with Analytical Predictions
Numerical Simulation of Puncture Tests
Evaluation of Transport Cask Impact Limiters
Performance Testing of West Valley Reference 6 Glass
Reactivity of Plutonium-Containing Classes for the Immobilization of Surplus Fissile Materials
Formation of Natural Analogues in Nuclear Waste Forms: A Geochemical Approach
Radionuclide Releases from Borosilicate and Natural Glasses
Reaction Progress Pathways for Glass and Spent Fuel Under Unsaturated Conditions
Aqueous Dissolution Rates of Uranium Oxides
Alteration of Spent Fuel Matrix Under Unsaturated Water Conditions
Actinide Source Term Predictions for Spent Fuel at Yucca Mountain
Performance Assessment Modeling of High Level Nuclear Wasteforms from the Pyroprocess Fuel Cycle
Bounding Potential Diesel Exhaust Impacts Produced From North Ramp Construction
A Dry Spent Nuclear Fuel Transfer System
Creep Strains Predicted from Constitutive Equations for Zircaloy-Clad Spent Fuel Rods
Designing Radiation Protection Signs
Use of HEPA Filters to Control Ionizing Radiation
Direct Burial of Industrial Plants by Mining
Alara Benefits of an MPC Robotic Welding System
System Safety Analysis of the Yucca Mountain Tunnel Boring Machine
Rh-Tru Transportation to the WIPP: Some Unresolved Issues
Requirements for the Emplacement of Doe-Owned Spent Nuclear Fuel into a Civilian Repository
Characterization of Aluminum-Uranium Core Fuels for Interim Dry Storage
Acceptance Criteria for Interim Dry Storage of Aluminum-Clad Fuels
Transitioning Aluminum Clad Spent Fuels from Wet to Interim Dry Storage
Evaluation of Degradation During Interim Dry Storage of Aluminum-Clad Fuels
Multi-Purpose Canister Project
An Evaluation of Dual-Purpose Canisters in the Civilian Radioactive Waste Management System
The IAEA Coordinated Research Programme on the Behaviour of Spent Fuel and Storage Facility Components During Long-Term Storage (BEFAST)
Spent Nuclear Fuel Behavior in Long-Term Dry Storage
Failure of MPC Overpack and Inner Container Under Corrosion and Mechanical Stresses in a Backfilled Drift
Finite-Element Analysis of Rock Drop Dynamic Loading on a Metallic Multi-Barrier Waste Package
Determination of SNF Peak Temperatures in the Waste Package
Materials Considerations for Interfaces Between Transportation, Storage and Disposal Systems
Leaching of Spent HEPA Filters for Cost Effective Disposal
Removal of Cesium and Strontium from Nuclear Wastes Using Solid Phase Extraction Membranes
Whole-Element Disposal of Plutonium-Consumption Modular Helium Reactor Spent Fuel
Assuring End-Game Integrity: Testbed Approach to Deployment of Detector Systems
Probabilistic Seismic Risk at Yucca Mountain From Published Data
Seismic Design Methodology for a Geologic Repository at Yucca Mountain
Mechanical Interaction Within Near-Field Behaviors of the Repositories
Experiences with Welding Multi-Assembly Sealed Baskets at Palisades
Multi-Purpose Canister Closure and Welding: Potential Automation and Impacts
Experimental Verification of Hydraulic Robot for Remote Handling of HLNW
Prototype Shield Plug Fabrication at the Oak Ridge Y-12 Plant
Andersson, Kjell
Lessons Learned in NEPA Public Involvement
Environmental Evaluations in the Multi-Purpose Canister Environmental Impact Statement
Providing Public Information for the Multi-Purpose Canister (MPC) Environmental Impact Statement (EIS)
Institutional and Technical Integration - The Real Meaning
Institutional and Technical Integration
Scientific Issues and Public Interactions: The Yucca Mountain Project
Communicating Human Factors Effects in Transporting Spent Nuclear Fuel
Cross Border Disposal of Radioactive Wastes Part I: Conceptual Study
Nuclear Waste Storage: A Legislative Issue
Building Trust and Confidence: The Long Road Ahead
Cross Border Disposal of Radioactive Wastes (Part II): Preliminary Case Study
Using Natural Analogue Studies in the Secondary Science Curriculum
The Development of Engineering Coursework on Nuclear Waste Management
A Decision-Making Students Project for Site Selection of HLW Repository
Education and Yucca Mountain
Incorporating Environmental Justice Measures During Environmental Impact Statement Scoping
Distance Learning and its Application to the Yucca Mountain Site Characterization Project
Managing High Level Nuclear Waste: Social, Economic, and Perceived Risk Issues
Rural Migration Decision Relating to Yucca Mountain
Explaining the Risks of Buried High Level Waste
A Comprehensive Set of Tools for Transportation Risk Assessment
One View of Risk Perception and Risk Communication
Risk Perception and Technical Interactions: Volcanism Studies for the Yucca Mountain Site Characterization Project
Empowerment: A Fundamental Tenet of Risk Communication and The Nimby Syndrome
Synthesizing Source Theories into Siting Interventions
Addressing New Policy Directions for Public Scoping: The Multi-Purpose Canister Environmental Impact Statement
A Public Informed on Nuclear Waste Issues Favors Reprocessing
Public Participation Practices at Work: The Process for Determining Site Suitability
An Evaluation of Alternative Models of Public Participation in Nuclear Waste Management and Cleanup of Federal Facilities
Site Characterization and Impact Study Prototype for Secondary Schools
Joint Spacing Criterion for Equivalent Continuum Model
The Influence of the 3-Dimensional Spatially Variable Rock Properties Upon Parameters Describing Upsacled Solute Transport
Sorption of Radionuclides at Tracer Level on Mineral Colloids
Colloid Stability in a Proposed Nuclear Waste Repository