Modelling Gas Migration Experiments in Repository
In response to concerns over the possibility of hydrogen gas generation within an underground repository for high-level radioactive waste, and its implications for repository safety, a...
The Nagra-DOE Cooperative Project
Tne Nagra-DOE Cooperative (NDC-I) research program was sponsored by the U.S. Department of Energy (DOE) through the Lawrence Berkeley Laboratory (LBL), and the Swiss Nationale Genossenschaft...
WAPPA Modeling of Post-Emplacement Performance of the AECL HLNW Package
Environment Canada (EC) is anticipating, in the near future, a review of the EIS document released by AECL which addresses the performance of their HLNW disposal concept. This paper presents...
Containment Barrier System Performance Assessment Modeling
A mathematical model to predict the cumulative failure distribution for the containment barrier system (CBS) employed in a deep geologic disposal facility is presented as a function of...
Prioritization of ESF Testing and Integration with Design and Construction
The developmental strategy for underground site characterization testing in the Exploratory Studies Facility (ESF) of the Yucca Mountain Site Characterization Program is outlined. The...
Operational Considerations in Drift Emplacement of Waste Packages
This paper discusses the operational considerations as well as the advantages and disadvantages of emplacing waste packages in drifts in a repository. The considerations apply particularly...
Robust Waste Package Concept (Multibarrier)
The design of the high level-waste package reflects the needs of the repository design and site conditions. As the program moves into the Advanced Conceptual Design (ACD) phase, different...
Post-Test Evaluations of Waste Isolation Pilot Plant?Savannah River Simulated Defense HLW Canisters and Waste Form
Eighteen nonradioactive defense high-level waste (DHLW) canisters were emplaced in and subjected to accelerated overtest thermal conditions for about three years at the bedded salt Waste...
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...
Implications of Stability Analysis for Heat Transfer at Yucca Mountain
An analytical solution has been obtained to the stability problem for an infinite horizontal layer of gas with its humidity constrained to 100%. Latent heat transfer makes convective heat...
Analyses of Natural Resources in 10 CFR Part 60 as Related to Inadvertent Human Intrusion
The purpose of this paper is to examine the intent of the regulatory language of the portions of 10 CFR Part 60 which deal with considerations of the natural resources of a proposed geologic...
New Directions for EPA's High-Level Waste Standards
Recently enacted legislation passed by the 102nd Congress directs a significant change in the Environmental Protection Agency's (EPA) development of standards for spent fuel, high-level...
Utility-DOE Interface Considerations of the Universal Container Systems Concept
This paper discusses the utility-DOE interface issues that must be addressed by the Department of Energy (DOE), the utility industry, and the Nuclear Regulatory Commission (NRC) prior...
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...
Post-Irradiation Fuel Assembly Dimensions for Transportation and Storage Cask Designs
When designing casks for the shipment of Spent Nuclear Fuel (SNF), one of the most important considerations is the external dimensions of the fuel assemblies to be shipped. Since SNF assemblies...
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...
1992: When Things Began to Move at Yucca Mountain
This paper examines progress made on the Yucca Mountain Site Characterization Project (YMP) during 1992 and continuing into 1993. In addition, it discusses and describes design work on...
Status and Progress Monitored Retrievable Storage Project
The past year has been substantive changes within the Monitored Retrievable Storage (MRS) Project. This paper will present the status of the Project, review the progress made over the...
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