Fire Retardant Treated Wood
The paper explains how FRTW chemicals react with combustible gases. It describes the two types into which FRTW is divided. Misconceptions about FRTW are also addressed....
Landslide Stabilisation at the Clyde Power Project, New Zealand
The Clyde Power Project is a hydro electric development on the Clutha River in the South Island of New Zealand. A wide range of stabilization measures have been used to treat several large...
Development and Evaluation of Remediation Strategies by Deformation Analysis
Deformation analysis is providing guidance for the most efficient and economical seismic remedial treatments for Mormon Island Auxiliary and Sardis dams. The computer program TARA-3FL...
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...
IAEA Activities in Long-Term Storage of Spent Fuel
According to its Statute, one of the main goals of the International Atomic Energy Agency (IAEA) is to accelerate and enlarge the contribution of Atomic Agency to peace, health and prosperity...
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...
Educational Programs at Penn State Breazeale Reactor?A Focus on Waste
Discussions about energy policy and issues focus on environmental impact of energy production and the generation of waste. When dealing specifically with nuclear energy, one of the major...
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...
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...
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...
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