New Advances in Shotcrete Additives: The DELVO System
The DELVO system is a two component, nonchloride chemical system developed to control the dynamics of cement hydration. Concrete, treated with the DELVO system, can be kept in a plastic...
MSA for VOC Removal
In what may be the first large-scale application of its type, mechanical surface aeration�usually used in wastewater treatment�is removing volatile organic compounds from potable ground...
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....
Fire Endurance Model for a Metal-Plate-Connected Wood Truss
A numerical model has been developed for predicting the fire endurance of a single metal-plate-connected wood truss. Extensive component fire testing was conducted to develop the necessary...
Time Variant Reliability Under Environmental Loads
Time variant reliability with deteriorating resistance under a stochastic load process is considered. An outcrossing formulation for fatigue degradation is presented, and a simple and...
Evaluation and Rehabilitation of Relief Wells
The U.S. Army Engineer District, Vicksburg has developed an expedient method of rehabilitating arrays of large numbers of gravity flowing relief wells located along the toe of dams using...
Shotcrete for Underground Support V
This proceedings consists of papers presented at the Engineering Foundation Conference held in Uppsala, Sweden on June 3-7, 1990. They are divided into sections concerned with the design...
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...
AREST: The Next Generation
Simple mass transport models using constant boundary conditions at the waste form surface and at the host rock boundary do not always results in realistic predictions of the performance...
An Assessment of Coupled Thermal-Hydrologic-Mechanical-Chemical Processes
A literature review was conducted to determine the state of knowledge available in the modeling of coupled thermal (T), hydrologic (H), mechanical (M), and chemical (C) processes relevant...
Geochemistry for High Level Waste: An International Comparison
This paper presents a brief summary of some of the recent and on going geochemical research related to the disposal of high level radioactive waste. For most categories of research (basic...
Experience in Modeling for Environmental Physics and Biogeochemistry
This report is a short review of the author's personal experience on phys.-math. and system-logical modeling of migration and transport processes (MTP) of radionuclides, trace-elements...
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...
Simulated Hanford Waste: A Study of Physical Properties, Gas Retention, and Gas Generation
This study helps to establish the physical and chemical processes responsible for the generation and retention of gases within high-level waste contained in Tank 101-SY on the Hanford...
Evaluation of Neutron Emission from Vitrified HLW Compositions
Neutron radiological hazards from vitrified HLW are important for handling and transportation - especially if the concept of separate storage of concentrated transuranics is adopted, as...
Use of Coupled Geochemical and Transport Calculations for Nuclear Waste Problems
The dissolution and migration of radionuclides from a final repository for radioactive waste is complex chemically. The dissolution and release rates depend on the chemistry and on advective...
Surface Complexation Model Prediction of Np and Pu Distribution Coefficients
Robust estimates of radionuclide sorption coefficients (Kd) are needed to estimate radionuclide retardation during ground-water transport from a...
??4U/??8U as a Ground-Water Tracer, SW Nevada-SE California
The 234U/238U ratio of uranium in oxidizing ground waters is potentially an excellent ground-water tracer...
Evaluation of Borosilicate Glass as a High-Level Radioactive Waste Form
The choice of a borosilicate glass as a high-level nuclear waste form is evaluated base on observations of natural and artifical glass hydration and reaction, experimental results of glass...
The Effect of Gamma Irradiation on the Volatility and Redox State of Simulated DWPF High-Level Nuclear Waste Glasses
Gamma-induced volatility of simulated DWPF high-level nuclear waste glasses is highly dependent upon the redox state of the glass. For oxidized glasses with an Fe2+/(Fe2+...
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