The Long Term Interim Storage of Spent AGR Fuel
This paper describes the work undertaken by Scottish Nuclear Ltd. on the proposal to construct a naturally cooled dry store for spent advanced gas cooled reactor fuel at Tornes Power Station,...
Interim Dry Storage of CANDU Fuel
The Canadian approach to permanent disposal of used CANDU fuel is directed toward its storage in suitable containers emplaced into an underground, stable, plutonic rock formation. Reprocessing...
Spent Fuel Interim Storage: French Experience with Dry Vaults
This paper explains the main criteria which are applied as well as measures taken to preserve cladding integrity for the foreseen duration of storage. It discusses in detail the double...
A Computer-Generated Film of Repository Operations
For the past fifteen years, the same types of questions concerning nuclear waste repository operations have kept coming up over and over again. What should be the average throughput for...
TVO-92 Safety Analysis of Spent Fuel Disposal
Spent fuel from the TVO I and TVO II reactors is planned to be disposed of in a repository to be constructed at a depth of about 500 meters in crystalline bedrock. The fuel will be encapsulated...
The Impact of Using Reduced-Capacity Baskets on Cask Fleet Size and Cask Fleet Mix
The Civilian Radioactive Waste Management System transportation system will encounter a wide range of spent fuel characteristics. Since the Initiative I casks are being designed to transport...
Review of International Near-Field Modelling for High-Level Waste Disposal
An international survey and review is being conducted on the latest developments in modelling of near-field performance, with particular emphasis on the conceptual and mathematical models...
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...
Maximum Individual Risks from Transported Spent Nuclear Fuel
The computer code TICLD (Transportation Individual Center Line Dose) is used with the computer code RADTRAN 4 to calculate maximum individual dose and risk from transportation accidents...
Route Selection Issues for NWPA Shipments
Questions surrounding the designation of routes for the movement of spent nuclear fuel (SNF) and high-level radioactive waste (HLW) by the Office of Civilian Radioactive Waste Management...
Significance of Campaigned Spent Fuel Shipments
Operational experience associated with spent fuel or irradiated hardware shipments to or from the General Electric Morris Facility is presented. The following specific areas are addressed:...
Hydrogeochemical Site Investigations by Teollisuuden Voima Oy, Finland
Groundwater samples collected from cored boreholes (500-1000 m), borehole wells and multilevel piezometers in crystalline bedrock have been characterized and classified. The reference...
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...
Status of WIPP Compliance with EPA 40 CFR 191B—December 1992
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...
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...
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