Waste Packager and Areal Power Density Approximator (WPA3) Computer Code
A microcomputer-based computer code called Waste Packager and Areal Power Density (APD) Approximator (WPA3) has been developed to compute waste package inventories and track individual...
An Assessment of Coupled Thermal-Hydrologic-Mechanical-Chemical Processes
A literature review was conducted to determine the state of knowledge available in the modeling of coupled thermal (T), hydrologic (H), mechanical (M), and chemical (C) processes relevant...
Regulatory Issues for WIPP Long-Term Compliance with EPA 40 CFR 191B and 268
Before disposing of transuranic radioactive waste at the Waste Isolation Pilot Plant (WIPP), the United States Department of Energy (DOE) must evaluate compliance with long-term regulations...
Standard Contract Issue Resolution Process: An Overview and Status
The Department of Energy has identified 35 issues associated with the Standard Contract for Disposal of Spent Nuclear Fuel and/or High-Level Waste (10 CFR Part 961) which need to be resolved...
Department of Energy Delivery Commitment Schedules for Spent Nuclear Fuel
The Delivery Commitment Schedule (DCS) provides Purchasers with the opportunity to inform the Department of Energy (DOE) of their plans for utilizing their allocations of projected spent...
Impact of Purchaser Selections of SNF for Delivery
This paper assesses aspects of work performed to determine operations requirements for the Transportation System (TS) that will ship spent nuclear fuel (SNF) and high-level radioactive...
Status of Cask Procurement Strategy to Satisfy DOE/OCRWM Requirements
The Nuclear Waste Policy Act requires the development of a safe and efficient system to transport spent nuclear fuel to and within the Federal Waste Management System. This paper describes...
Management of Spent Nuclear Fuel in Sweden?Experiences and Plans
The principle adopted for the management of spent nuclear fuel from the Swedish reactors is final disposal without reprocessing. During the 1980ies systems and facilities for the transport...
Taipower's Spent Fuel Interim Storage Program
Given the original designs, the existing six nuclear power units of Taiwan Power Company will lose full core discharge capability before end 1990's. To timely fulfill additional spent...
Multi-Purpose Canisters as an Alternative for Storage, Transportation, and Disposal of Spent Nuclear Fuel
A study was conducted to assess the feasibility of using multi-purpose canisters to handle spent nuclear fuel throughout the Civilian Radioactive Waste Management System. Multi-purpose...
Comparison of Predicted Far-Field Temperatures for Discrete and Smeared Heat Sources
A fundamental concern in the design of the potential repository at Yucca Mountain, Nevada is the response of the host rock to the emplacement of heat-generating waste. The thermal perturbation...
The Analysis of Repository-Heat-Driven Hydrothermal Flow at Yucca Mountain
To safely and permanently store high-level nuclear waste, the potential Yucca Mountain repository site must mitigate the release and transport of radionuclides for tens of thousands of...
The Results of Near-Field Thermal and Mechanical Calculations of Thermal Loading Schemes
Two waste emplacement schemes, borehole and in-drift, are under evaluation as potential repository drift geometries for the Yucca Mountain Site Characterization Project. Calculations were...
Systems Implications of Repository Thermal Loading
A study was conducted to determine if implementation of a hot, cold or intermediate repository thermal loading strategy would have specific impacts on the overall Civilian Radioactive...
Spent Fuel Assembly Source Term Sensitivity Parameters: SAND92-2113C TTC-1225
Containment of cask contents by a transport cask in a function of the cask body, one or more closure lids, and various bolting, hardware, and seals associated with the cavity closure and...
Investigation in 3-D of Stress Distribution in a Circular Tunnel and Vertical Emplacement Holes Due to Thermal and Overburden Loading in Tuff
Thermal stress and displacement analysis using two 3-D finite element models, one having a course mesh and one having a highly detailed mesh are presented. Results are compared to those...
Rock Mass Mechanical Property Estimation Strategy for the Yucca Mountain Site Characterization Project
Rock mass mechanical properties are required in the design of repository drifts and ramps to assess the impact of thermal loads from the heat-generating wastes on excavation performance...
Instrumentation Requirements for the ESF Thermomechanical Experiments
In situ thermomechanical experiments are planned as part of the Yucca Mountain Site Characterization Project that require instruments to measure stress and displacement at temperatures...
Single-Hole in Situ Thermal Probe for Hydrothermal Characterization at Yucca Mountain
The REKA thermal probe method, which uses a single borehole to measure in situ rock thermophysical properties and provides for efficient and low-cost site characterization, is analyzed...
The Swedish Dialogue Project. An Attempt to Explore How Different Actors May Take Part in the Decision Process Related to Disposal of Radioactive Waste
The Swedish Nuclear Power Inspectorate (SKI) has initiated a project, DIALOGUE, which is exploring the possibility to define review procedures for license applications of nuclear waste...
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