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A Preliminary Model for Carbon-14 Transport in a Clay Buffer
A model has been developed to assess the effect of calcite dissolution and precipitation reactions on the transport of ¹⁴C through a saturated, calcite-containing...

Natural Radionuclides in Groundwater From J-13 Well at the Nevada Test Site
The concentrations of U-238 and Th-232 chain members are extremely low in J-13 water, suggesting that their concentrations in groundwaters are largely governed by sorption/desorption processes....

One-Dimensional Radionuclide Transport Under Time-Varying Conditions
New analytical and numerical solutions are presented for one-dimensional radionuclide transport under time-varying fluid-flow conditions including radioactive decay. The analytical solution...

Simulation of Radionuclide Retardation at Yucca Mountain Using a Stochastic Mineralogical/Geochemical Model
This paper presents preliminary transport calculations for radionuclide movement at Yucca Mountain using preliminary data for retardation parameter distributions based on mineral distributions....

Radioactive Materials Packaging Standards and Regulations?Making Sense of it All
Numerous regulations and standards, both national and international, apply to the packaging and transportation of radioactive material. These are legal and technical prerequisites to practically...

Public Concerns of Nuclear Waste Issues in Taiwan
Opinions and comments from randomly selected 1837 general public and 454 professionals are compiled and analyzed to obtain their concerns on nuclear waste issues in Taiwan. Results indicate...

U.S. Department of Energy Motor Carrier Evaluation Program
The U.S. Department of Energy-Headquarters (DOE-HQ), Transportation Management Division (TMD) has the overall responsibility to provide a well-managed transportation program for the safe,...

Selecting Preferred Routes for Highway Route Controlled Quantity Shipments of Radioactive Materials
The amount of spent nuclear fuel move in the U.S. in recent years has increased due to a number of government actions. One such action was the passage of the Nuclear Waste Policy Act which...

Nagra Performance Assessment of Radioactive Waste Disposal in Crystalline and Sedimentaly Host Rocks
Nagra has evaluated disposal of vitrified HLW in both the crystalline basement of Northern Switzerland and in overlying argillaceous sedimentary formations. Although indicating that both...

Initiating Event Identification and Screening for Nuclear Waste Repository Preclosure Risk Assessment
This paper describes a method to identify potential initiating events that might occur during the preclosure phase at a nuclear waste repository proposed for the Yucca Mountain area of...

Status of Integrated Performance Assessment of the Waste Packages and Engineered Barrier System
Performance assessment of the engineered barrier system for a nuclear waste repository combines information from relevant disciplines and predicts the net long-term performance of the...

Mass-Transfer Analysis of Waste Packages Containing Defense Waste Processing Facility Glass as a Waste Form
The fractional release rates of selected radionuclides from waste packages containing Defense Waste Processing Facility (DWPF) glass are calculated using the AREST code, assuming a continuous-diffusive...

A Gas-Flow Source Term from a Nuclear Waste Container in an Unsaturated Medium
The potential nuclear waste repository at Yucca Mountain is to be in partially saturated rock. Released radioactive gases would have a direct pathway to the biosphere. The entry of air...

?⁴C Release From Failed Spent Fuel Containers
Partially failed containers may provide a meaningful barrier to the release of gaseous radionuclides. A modeling approach is outlined and sample calculations are provided that show the...

Container Material Selection, Modeling and Testing
Virtually all of the approximately 40,000 high-level nuclear wast containers to be emplaced at Yucca Mountain must remain intact for 1,000 years to satisfy Nuclear Regulatory Commission...

MIIT; International In-Situ Testing of Simulated HLW Forms?Preliminary Analyses of SRL 165/TDS Waste Glass and Metal Systems
The first in-situ tests involving burial of simulated high-level waste (HLW) forms conducted in the United States were started on July 22, 1986. This effort, called the Materials Interface...

Role of Waste Packages in the Safety of a High Level Waste Repository in a Deep Geological Formation
The safety of a radioactive waste disposal facility lays on the three following barriers placed between the radioactive materials and the biosphere: the waste package, the engineered barriers,...

The Continuing Evolution of a Radioactive Material Transport System
The paper considers the evolution of BNFL's transportation system and those lessons learned and incorporated or being incorporated in the system as it continues to evolve....

TN28V High Capacity Cask for the Transport and Storage of Vitrified Wastes
When the option of reprocessing has been selected, closing of the fuel cycle implies the return shipment of reprocessing wastes back to the country of origin of the spent fuel, in particular...

Surface-Based Site Characterization Testing to Determine the Suitability of the Yucca Mountain Site for a Nuclear Waste Repository
The Yucca Mountain Site in Nevada is currently being evaluated by the U.S. Department of Energy to determine its suitability for the first U.S. high-level radioactive waste repository....

 

 

 

 

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