The removal of CO/sub 2/ from air in a calcium hydroxide slurry-agitated reactor was investigated to aid the design of such vessels. Gas-liquid interfacial areas were calculated using theoretical rate expression and experimental data at specific operating conditions. A correlation for interfacial areas was then determined as a function of impeller speed, impeller diameter, gas flow rate, and concentration of the slurry. Decontamination factors were also determined.

To minimize the radiological risk from the operation of a waste management system for the safe disposal of high-level waste, performance characteristics of the solidified waste form must be specified. The minimum waste form characteristics that must be specified are the radionuclide volatilization fraction, airborne particulate dispersion fraction, and the aqueous dissolution characteristics. The results indicate that the pre-emplacement environs are more limiting in establishing the waste form performance criteria than the post-emplacement environs. The actual values of expected risk are sensitive to modeling assumptions and data base uncertainties. The transportation step appears to be the most limiting in determining the required performance characteristics.

In order to obtain access to a computer from ordinary NDT instruments, a special interface was made which acts as the buffer between the computer, and the real world. The special purpose interface, which was designed and built by Group M-1 of the Los Alamos Scientific Laboratory is described. This interface was primarily built for use with various ultrasonic equipment, but is actually a general purpose system that can perform data acquisition and control for other tests.

The sphere-cylinder method of using nuclear magnetic resonance (NMR) to measure the magnetic susceptibility of diamagnetic and paramagnetic materials has been generalized to the disk-cylinder method. A two-fold increase in sensitivity was obtained. Accuracies of 0.1% of the diamagnetism of water should be readily obtainable.

Most of the Dilute Chemical Decontamination Program effort was expended on the VNC test loop simulation of a BWR decontamination. The various tasks in the Alternate Water Chemistry Program are reported on: dose rate, offgas system, leakage monitoring, materials, condensate treatment, additives, etc. (DLC)

As indicated by tests on several cameras, the dynamic range of the Lawrence Livermore Laboratory streak-camera system appears to be about two orders of magnitude greater than those reported for other systems for 10- to 200-ps pulses. The lack of a fine mesh grid in the RCA streak tube used in these cameras probably contributes to a lower system dynamic noise and therefore raises the dynamic range. A developmental tube with a mesh grid was tested and supports this conjecture. Order-of-magnitude variations in input slit width do not affect the spot size on the phosphor or the dynamic range of the RCA tube.

The development of a high-frequency electronic (Stevens) ballast for fluorescent lamps is described. It is claimed that use of this ballast could reduce use energy consumption by 1.2 to 2.5 percent. The Stevens ballast has a basic efficiency of 29 percent when used with conventional lamps. With the more efficient lamps, the efficiency increases drastically. The conventional ballast and lamp has an efficiacy of approximately 60 to 63 lumens per watt (LPW). With the Stevens ballast the efficiacy raises to between 75 and 80 lumens per watt. When the Stevens ballast is utilized with the newer high efficiency lamps the efficiacy increases to 90 to 95 lumens per watt or a full 51 percent improvement over conventional coil and core ballasts and 25 percent over the best high efficiency premium coil and core ballasts. In addition to its energy savings capabilities, this high frequency fluorescent lamp ballast has the advantages that it is a true retrofit device that is directly interchangeable with the conventional coil core ballast, and it is dimmable over a wide and continuous range. (LCLC)

This study was conducted to identify processes that are most applicable for control of H/sub 2/S from geothermal sources. Both vapor-dominated and liquid-dominated sources were considered within the electric power generation category. The source characteristics, H/sub 2/S control requirements, and applicable technologies are discussed for the two geothermal sources. An evaluation of the applicable control technology indicates that there are three major approaches for H/sub 2/S removal. These are (a) upstream cleaning (ahead of the power plant), (b) removal of H/sub 2/S from condenser vent emissions, and (c) H/sub 2/S removal from cooling water, including condensate. The most promising processes for these emission points, based on current information, are as follows: the EIC process for upstream cleaning of liquid-dominated sources. For condenser vent emissions, the Stretford process appears to be most applicable; for cooling tower emissions, the iron catalyst process, followed by the H/sub 2/O/sub 2/ process, seems most appropriate.

This Gruy Federal Type I-A prospect was drilled as the Union Oil Company of California, Dr. M.O. Miller No. 1 and is located in Section 34, T15S, R5W, Cameron Parish, Louisiana. The land belongs to the heirs of Dr. Miller and is unleased. The well site is approximately 350 feet southwest of the northwest corner of Section 34 and approximately 4,000 feet south-southeast of Prospect L-3, Buttes Gas and Oil Co. et al., Gladys McCall No. 1. The former well site is accessible by approximately 2.8 miles of canal levee on which a board road would have to be constructed. In addition, there are two wooden bridges in fair condition to be crossed which will require minor repairs. The well was drilled to a total depth of 18,158 feet and plugged and abandoned as a dry hole mid 1965.

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This detailed report on Lawrence Livermore Laboratory's control program to minimize beryllium levels in Laboratory workplaces includes an outline of beryllium surface, soil, and air levels and an 11-y summary of sampling results from two high-use, high-explosive test firing bunkers. These sampling data and other studies demonstrate that the beryllium control program is funcioning effectively.

The stability of a liquid-lithium jet flow is of importance in a laser fusion reactor design. In this report we analyze and discuss jet stability with respect to fluid dynamics, delineating physical factors that may affect the jet breakup and performing some simple calculations to determine quantitatively the relative influences of various parameters. We define areas of uncertainty and recommend possible experimental verification, theoretical analysis, or both.

Performance models for a two-phase turbine were developed to verify the understanding of the loss mechanisms and to extrapolate from the single-nozzle test condition to a full-admission turbine. The numerical models for predicting the performance of the nozzle and the combined nozzle and rotor are described. Results from two-phase, static cascade tests and disk-friction and windage experiments are used to calibrate the performance model(s). Model predictions are compared with single-nozzle prototype-turbine test results, and extrapolations are made to a full-admission design. The modeling also provides predictions of performance for turbines with various blade geometries, inlet conditions, and droplet sizes. Thus the modeling provides insight into design improvements.

A modified wire drawing die for spatial filtering techniques is described. It was designed for use in high power laser systems. The diamond aperture is capable of enduring high intensity laser frequency without damaging the laser beam profile. The diamond is mounted at the beam focus in a vacuum of 1 x 10/sup -5/ Torr. The vacuum prevents plasma forming at the diamond aperture, thus enabling the beam to pass through without damaging the holder or aperture. The spatial filters are fitted with a manipulator that has three electronic stepping motors, can position the aperture in three orthogonal directions, and is capable of 3.2 ..mu..m resolution. Shiva laser system is using 105 diamond apertures for shaping the High Energy Laser Beam.

The energy spectra of low-intensity neutron sources used for calibrating personnel neutron dose-rate meters and dosimeters and for characterizing the neutron fields to which personnel are exposed were measured. Several detector-analyzer systems that will measure in the energy range 50 keV to 20 MeV at intensities from 10/sup -1/ to 10/sup 5/ n/cm/sup 2/-s are described. The systems include NE213 and stilbene organic scintillators as well as H/sub 2/, /sup 3/He, and CH/sub 4/ proportional counters. Also described are pulse-height analysis and pulse-shape discrimination systems. An unfolding code, NUTSPEC, reduces the pulse-height data to an absolute differential neutron flux phi(E) for the above detectors. The code uses a derivative unfolding method for the scintillation detectors, and for the proportional counters it calculates a response matrix and uses an iterative unfolding method to determine phi(E). The unfolded flux distribution combined with published conversion factors produces differential neutron dose-equivalent and kerma rates. Spectral segments obtained with different detectors from several measurements merge into a single differential flux spectrum over the range 50 keV to 20 MeV, together with the corresponding differential kerma and neutron dose-equivalent distributions. Also reported are spectrum measurements near /sup 252/Cf and /sup 238/PuBe sources with various moderators.

A New Waste Calcining Facility is being built at the Idaho Chemical Processing Plant to replace the existing Waste Calcining Facility which was built to demonstrate fluidized-bed solidification of highly radioactive liquid wastes. The new facility is being designed to provide a higher waste throughput, more corrosion resistant materials of construction, more effective cleanup of effluent streams, and extensive remote maintenance and equipment replacement capability. The facility will also contain extensive decontamination capability should contact maintenance become necessary. The facility is presently in construction and is scheduled for hot operation in 1980.

A unique pure reaction turbine, for geothermal applications, has been developed. This radial outflow reaction turbine (RORT) is designed specifically to produce power from the expansion of saturated or compressed liquid at temperatures of less than 180/sup 0/C. In the tests reported here the highest efficiency measured was 32.7%, clearly below the peak efficiency for this small machine. Extrapolations to larger machines indicate that an efficiency near 50% is a credible goal, an attractive performance as either a Total Flow expander for liquid or in conjunction with conventional flashed steam systems. A rough cost estimate indicates that a 7.5 MW RORT would cost somewhere between 0.5 M$ and 1.5 M$, and could add about 15% increase in the power output of a conventional 50 MW plant. This means that for less than a 3% increase in capital cost the bus bar energy cost can be reduced by about 10%. Another important result is that the RORT is uniquely suited for conversion of the thermal and pressure energy components in the geopressured resources. The development and proof of feasibility of efficient liquid expanders broadens the opportunities for economic power production from lower temperature geothermal resources, and possibly utilization of waste heat …

Efforts devoted to searches for short-lived nuclides in the debris from large thermonuclear explosions are reviewed along with reactor production of Es and Fm. Results of underground tests are discussed along with odd-even yield variations, and future directions for heavy-element synthesis. (JRD)

The overall purpose of this meeting is to discuss the report that was sent to PG and E on February 1st discussing Geysers 17. The Commission has reviewed all of the existing data, the majority of the existing data that have gone through both Lake County and through the CPUC regarding 17, looked at the existing data to see what, if any, additional would be required to file and expeditiously process a Notice of Intention on Geysers Unit 17.

This specification defines the requirements for the Intermediate-Size Inducer Pump (ISIP), which is to be made by replacing the impeller of the FFTF Prototype Pump with a new inducer, impeller, diffuser, seal, and necessary adapter hardware. Subsequent testing requirements of the complete pump assembly are included.

The objectives of the program are to conduct tests that will characterize the behavior of sodium oxide, fuel, fission product, and other aerosols as they might be generated by various postulated LMFBR accidents; determine by analysis and confirm by experiment the generation and transport of these aerosols with respect to source (location, type, and configuration), for the entire course of events associated with real and hypothetical accident conditions; and conduct tests that will determine the effect of molten fuel on reactor structural or sacrificial material.

Lists of documents exchanged during the second half of 1977 under agreements between the U.S. Nuclear Regulatory Commission's Office of Nuclear Regulatory Research and the governments of France, Federal Republic of Germany, Japan, and the United Kingdom are presented. During this period, the NRC received 1 report from France, 40 from the Federal Republic of Germany, and 11 from Japan, and in return sent 112 U.S. reports to each of these three countries and 23 reports to the United Kingdom.

Methods of integrating data from the Near-Surface Test Facility into the overall Waste Isolation Program are examined. Discussions are presented dealing primarily with the application of numerical models to the design of a waste repository. The various types of models currently available are discussed with reference to design in basalt and the breakdown of the problem of repository design is summarized. It is shown that the most efficient method for analyzing repository design is to break the problem down into several problems which are based on physical scale. These include the area directly surrounding a single waste canister (the very near field), the area including many canisters and canister emplacement rooms (the near field), and the area including the entire repository and the rock mass to the free surface (the far field). The methods by which numerical models are used for design are discussed. Flow charts are used to show the basic input data required, the calculational processes used, and the preliminary criteria for judgment of suitable repository performance. It is shown that the ultimate design of the allowable gross thermal loading density, and, thus, the layout of the underground workings is highly dependent upon the rock mass properties supplied …

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