Proceedings of the 1978 Symposium on Instrumentation and Control for Fossil Demonstration Plants : June 19-21, 1978, Newport Beach Marriott, Newport Beach, California (open access)

Proceedings of the 1978 Symposium on Instrumentation and Control for Fossil Demonstration Plants : June 19-21, 1978, Newport Beach Marriott, Newport Beach, California

This conference covers various aspects of fossil-fuel power plants based on coal or coal-conversion products, as well as the process control equipment involved in the conversion or combustion processes.
Date: June 1978
Creator: Argonne National Laboratory
System: The UNT Digital Library
Radiological and Environmental Research Division Annual Report: Part 2, Center for Human Radiobiology, July 1977-June 1978 (open access)

Radiological and Environmental Research Division Annual Report: Part 2, Center for Human Radiobiology, July 1977-June 1978

Annual report of the Argonne National Laboratory Radiological and Environmental Research Division regarding activities related to the Center for Human Radiobiology.
Date: June 1978
Creator: Rowland, R. E.
System: The UNT Digital Library
Decommissioning Alternatives for the West Valley, New York, Fuel Reprocessing Plant (open access)

Decommissioning Alternatives for the West Valley, New York, Fuel Reprocessing Plant

The methodology and numerical values of NUREG-0278 were applied to four decommissioning alternatives for the West Valley Fuel Reprocessing Plant. The cost and impacts of the following four alternatives for the process building, fuel receiving and storage, waste tank farm, and auxiliary facilities were assessed: (1) layaway, (2) protective storage, (3) preparation for alternate nuclear use, and (4) dismantlement. The estimated costs are 5.7, 11, 19, and 31 million dollars, respectively.
Date: June 1978
Creator: Munson, L. F.; Nemec, J. F. & Koochi, A. K.
System: The UNT Digital Library
A Nodal Method for Solving Transient Fewgroup Neutron Diffusion Equations (open access)

A Nodal Method for Solving Transient Fewgroup Neutron Diffusion Equations

A nodal method for multidimensional light water reactor (LWR) static and transient analysis is presented in this report. This method efficiently solves one- or two-group diffusion equations using an analytic solution procedure. This report details significant improvements made to those aspects of the method previously reported in the literature. Eigenvalues and power distributions are presented for several static benchmark problems. Time-dependent results for a difficult two-dimensional BWR kinetics benchmark problem are presented. A reference solution for this benchmark problem is also presented. The results presented in this report are summarized, and suggestions are made as to appropriate ways to extend this work to multi-group fast breeder reactor analysis.
Date: June 1978
Creator: Shober, R. A.
System: The UNT Digital Library
PROSA-1 : a Probabilistic Response-Surface Analysis Code (open access)

PROSA-1 : a Probabilistic Response-Surface Analysis Code

Techniques for probabilistic response-surface analysis have been developed to obtain the probability distributions of the consequences of postulated nuclear-reactor accidents. The uncertainties of the consequences are caused by the variability of the system and model input parameters used in the accident analysis. Probability distributions are assigned to the input parameters, and parameter values are systematically chosen from these distributions. These input parameters are then used in deterministic consequence analyses performed by mechanistic accident-analysis codes. The results of these deterministic consequence analyses are used to generate the coefficients for analytical functions that approximate the consequences in terms of the selected input parameters. These approximating functions are used to generate the probability distributions of the consequences with random sampling being used to obtain values for the accident parameters from their distributions. A computer code PROSA has been developed for implementing the probabilistic response-surface technique. Special features of the code generate or treat sensitivities, statistical moments of the input and output variables, region-wise response surfaces, correlated input parameters, and conditional distributions. The code can also be used for calculating important distributions of the input parameters. The use of the code is illustrated in conjunction with the fast-running accident-analysis code SACO to provide probability …
Date: June 1978
Creator: Vaurio, J. K.; Mueller, C.; Kyser, J. M. & Sciaudone, D.
System: The UNT Digital Library
Simple Procedure for Predicting Long-Term Average Performance of Nonconcentrating and of Concentrating Solar Collectors (open access)

Simple Procedure for Predicting Long-Term Average Performance of Nonconcentrating and of Concentrating Solar Collectors

The Liu and Jordan method of calculating long term average energy collection of flat plate collectors is simplified (by about a factor of 4), and generalized to all collectors, concentration and non-concentrating. The only meteorological input needed are the long term average daily total hemispherical insolation H/sub h/ on a horizontal surface and, for thermal collectors the average ambient temperature. The collector is characterized by optical efficiency, heat loss (or U-value), heat extraction efficiency, concentration ratio and tracking mode. An average operating temperature is assumed. Interaction with storage can be included by combining the present model with the f-chart method of Beckman, Klein and Duffie. Formulas and examples are presented for five collector types: flat plate, compound parabolic concentrator, concentrator with E.-W. tracking axis, concentrator with polar tracking axis, and concentrator with two axis tracking. The examples show that even for relatively low temperature applications and cloudy climates (50 degrees C in New York in February), concentrating collectors can outperform the flat plate. The method has been validated against hourly weather data (with measurements of hemispherical and beam insolation), and has been found to have an average accuracy better than 3% for the long term average radiation available to solar …
Date: June 1978
Creator: Collares-Pereira, Manuel & Rabl, Ari
System: The UNT Digital Library
Binary Solution Model for Computation of Equilibrium Compositions (open access)

Binary Solution Model for Computation of Equilibrium Compositions

A NASA computer program (CEC) for calculation of complex equilibrium compositions has been modified to take into account the formation of an ideal binary solution from pure condensed species. The thermodynamics of the modification are discussed. Applications are presented.
Date: June 1978
Creator: Hsu, Chen C.; Land, Robert H. & Blander, Milton
System: The UNT Digital Library
Chemical Activities of Alkali Sulfates in Hot Corrosion (open access)

Chemical Activities of Alkali Sulfates in Hot Corrosion

The condensation temperatures of sodium and potassium sulfates from typical fuel-oil combustion gases were calculated as functions of the concentrations of SO2, HCl, NaCl and O2, and total combustion pressures ranging from 1 to 10 atm. Of these components, oxygen had the greatest effect on the condensation temperature of sodium sulfate, producing an increase of as much as 280 degrees K at 10 atm. Alkali sulfate activities were least affected by sulfur dioxide, tested in the range from 93 to 270 ppM. The order of the effect on the alkali sulfates was as follows: O2 > HCl > NaCl > SO2. With the addition of K2CO3, such as would occur in the magnetohydrodynamic (MHD) environment, the activity of potassium sulfate overshadowed that of sodium sulfate. The control of the activities of alkali sulfates is discussed in terms of the concentrations of the above-mentioned species and of the system pressure.
Date: June 1978
Creator: Hsu, Chen C.; Johnson, Irving & Blander, Milton
System: The UNT Digital Library