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...
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...
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...
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...
Nuclear Fuel Waste Disposal: The Canadian Consultative Approach
Over the past two decades society has demanded more public participation and public input into decision-making by governments. Accordingly, development of the Canadian concept for deep...
Perspectives on Out-of-Pool Spent Fuel Storage Requirements 1992-2036
The estimates of requirements for additional storage capacity for spent nuclear fuel from commercial LWRs in the United States are examined in this study. A comparison of this study's...
Disposal of Defense Spent Fuel and HLW from the Idaho Chemical Processing Plant
Acidic high-level radioactive waste (HLW) resulting from fuel reprocessing at the Idaho Chemical Processing Plant (ICPP) for the U. S. Department of Energy (DOE) has been solidified to...
The Effect of Certain Assumptions on the Number and Type of Spent Fuel Casks Required 1998-2000
The Office of Civilian Radioactive Waste Management M&O contractor is determining the number of spent fuel transportation cask systems required to transport fuel from reactors...
Systems Integration and Economic Aspects of the Universal Container System
Universal containers (UC) are multi-assembly spent fuel containers that are loaded and sealed at reactor sites or the first DOE facility. They are thereafter handled as clean containers...
Plutonium and Minor Actinide Transmutation by Long Irradiation in LWR
An investigation was made on the conceptual possibility of burning in a thermal reactor MOX fuel together with special pins containing plutonium, minor actinides and long-lived fission...
Remote Spent Fuel Handling in France at the La Hague Cask Unloading Facility
French policy for the back end of fuel cycle is based on spent fuel reprocessing. Irradiated spent fuels are transferred in casks from the nuclear reactors to the reprocessing plant where...
Demonstration of a Transportable Storage System for Spent Nuclear Fuel
The ultimate disposal of spent nuclear fuel is a major issue that continues to plague the nuclear industry and the Department of Energy (DOE). In an effort to resolve some of the outstanding...
System Impacts on MRS Operations
This paper describes the results of analyses conducted to evaluate impacts on monitored retrievable storage (MRS) operations and design resulting from possible changes in the CRWMS Reference...
Human Factors Engineering Applications to the Cask Design Activities of the Civilian Radioactive Waste Management Program
The use of human factors engineering (HFE) in the design and use of spent fuel casks being developed for the Department of Energy's Civilian Radioactive Waste Management Program is addressed....
Evaluation of Spent Fuel Behavior Under Interim Storage Conditions in Russia
The nuclear power in Russia is based on three types of water cooled power reactors VVER-440, -1000 and RBMK-1000. Two fast sodium cooled reactors-prototypes BN-350 and BN-600 are in commercial...
Assessments of System Impacts of Spent Fuel Thermal Characteristics and Emplacement Rates
Analyses conducted to evaluate the impacts spent fuel thermal characteristics and emplacement rates might have on the thermal conditions in a candidate geologic repository at the Yucca...
Shielding Benchmark Calculations of Selected Spent Fuel Storage Cask Experiments
This paper describes the application of the three-dimensional Monte Carlo code MORSE-SGC, as implemented in the SCALE system calculational sequence SAS4, to the analysis of a series of...
Verification of Shielding Analysis for Spent Fuel Storage Casks
Casks of type CASTOR are used for transport and storage of spent LWR fuel assemblies. The purpose of the present work is the verification of shielding design analysis methods by application...
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