Rehabilitation of Plane Nine Dam
Plane Nine Dam, an earthen water supply dam near Altoona, Pennsylvania, was constructed in 1907. The dam performed satisfactorily for more than 80 years but it deteriorated with time and...
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,...
Hanford Waste Vitrification Project Overview and Status
The Hanford Waste Vitrification Project (HWVP) is being constructed at the U.S. Department of Energy's Hanford Site in Richland, Washington. The paper gives an overview of the HWVP which...
Human Factors Engineering Program Plan for the Hanford Waste Vitrification Plant
The paper describes the overall human factors program plan while providing more specific information regarding the critical areas of criteria development, dispersed control areas and key...
The Impact of Safety Analyses on the Design of the HWVP Vitrification Plant
Accident analyses are being performed to evaluate and document the safety of the Hanford Waste Vitrification Plant (HWVP). The effects of worst-case accident scenarios are evaluated by...
Application of Monte Carlo Neutron Photon to Hanford Waste Vitrification Plant Design Analysis
The Monte Carlo Neutron Photon (MCNP) computer program ('MNCP - A General Monte Carlo Code for Neutron and Photon Transport, Version 3A') (in PC and mainframe versions) has been used for...
Installation and Routing of Critical Embedments at the Hanford Waste Vitrification Plant
During the preliminary design phase of the project, a study was conducted to develop concepts for routing embedded piping and conduit between the remote cells and the service corridors...
Glass Melter Assembly for the Hanford Waste Vitrification Plant
The Hanford Waste Vitrification Plant (HWVP) is designed to solidify high level radioactive waste by converting it into stable borosilicate glass after mixing with glass frit and water....
Mechanical Design of the Storage Tubes in the HWVP Canister Storage Building
Canisters of high-level waste from the Hanford Waste Vitrification Plant (HWVP) will be stored in an adjacent facility, the Canister Storage Building (CSB). The canisters are stored vertically...
Carbon-14: Some Evidence of Migration and Experiments on Immobilisation
Carbon-14 that is produced in nuclear reactors by reactions on C, N and O is one of the most biologically dangerous nuclides that are subject to global dispersion (H-3, 85-Kr, 129-I)....
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...
Code Requirement for Concrete Repository and Processing Facilities
Because of varied uses and performance/safety requirements of concrete for high, medium and low level radioactive wastes, a review of the current ACI 349 Code document was carried out...
Radionuclide Transport in Fractured Media
Until recently, the classical advective-dispersive transport equation was considered to be an adequate model for describing the motion of a solute (e.g. radionuclides) in porous and fractured...
Quality-Assurance Program Description Defense Waste Processing Facility
This paper describes the Westinghouse Savannah River Company's (WSRC) quality assurance program for defense-waste processing at the Savannah River Site (SRS). WSRC is the operating contractor...
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...
ATW System Impact on High-Level Waste
Criteria are developed for transmutation system impact on HLW storage that are related to intrusion and long-term risk reduction. Thermal reactor, fast reactor, and accelerator-driven,...
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...
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...
HWVP Compliance with the Hanford Site Solid Waste Acceptance Criteria
This report describes the Hanford Waste Vitrification project (HWVP), which will be located at the Haford Site. The Hanford Site encompasses a 560-mi2...
Tolerance Requirements for Remote Handling at the Hanford Vitrification Project
A new and innovative approach to installation of the many remote nozzles and electrical connectors that must be installed to demanding tolerances has been developed by the architect/engineer...
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