An anion exchange process was developed to process miscellaneous residues of plutonium plus 0.5 wt % neptunium to allow prompt return of the plutonium to a plutonium recovery process. Several macroreticular anion exchange resins were compared to Dowex 1-X4 for the process. Dowex 1-X4 showed the best performance for the plutonium (III)-neptunium(IV) separation.

This document contains the Work Plan for the modification of the AI Steam Generator for tests in Large Leak Test Rig. This Work Plan describes the objectives, scope of work, schedule and manpower, end items, and meetings and reports required for the modification.

Papers are presented on research programs concerned with underground storage of radioactive wastes. A separate abstract was prepared for each of twenty-three papers. (JRD)

As now being explored for fusion applications confinement systems based on the mirror principle embody two kinds of plasma regimes. These two regimes are: (a) high-beta plasmas, stabilized against MHD and other low frequency plasma instabilities by magnetic-well fields, but characterized by non-Maxwellian ion distributions; (b) near-Maxwellian plasmas, confined electrostatically (as in the tandem mirror) or in a field-reversed region within the mirror cell. Common to both situations are the questions of anomalous transport owing to high frequency instabilities in the non-maxwellian portions of the plasmas. This report will summarize the status of theory and of experimental data bearing on these questions, with particular reference to the high temperature regimes of interest for fusion power.

We discuss the statics and dynamics of large scale nuclear collective motion, with special emphasis on very-heavy-ion reactions. Compound-nucleus cross sections are calculated by use of the criterion that the dynamical trajectory for the fusing system must pass inside the fission saddle point in a multidimensional space in order to form a compound nucleus. In an effort to understand whether nuclear dissipation is dominated by two-body collisions or by the interaction of particles with the mean field generated by the remaining particles, we compare the predictions of various macroscopic approaches with those of time-dependent mean-field (Hartree-Fock) theories.

The standard colorimetric procedure for thorium was improved by using lanthanum carrier precipitation of thorium fluoride, conversion to sulfate, and colorimetric measurement with thoron. Four types of anion-exchange resins were evaluated using breakthrough capacity, elution volume, and the neptunium-plutonium ratios in both wash solutions and ion-column eluates as criteria, and 100 to 200 mesh Dowex 1 x 4 resin had the most favorable separation characteristics. Use of commercially available aqueous cleaner followed by water and acetone rinses was found to be superior to other techniques for cleaning uranium samples prior to carbon analysis. The substitution of sodium bisulfate for potassium pyrosulfate in the fusion procedure has lead to a more efficient dissolution process for oxide samples undergoing plutonium assay and the determination of uranium impurities. Sealed-capillary differential thermal analysis experiments were performed to assess the relative reactivities of iron, stainless steel, copper, beryllium, aluminum, and plutonium with trichloroethylene, methyl chloroform, and Freon TF. Results obtained by a method involving reduction of plutonium with titanium (III) chloride followed by titration with standard cerium (IV) sulfate solution are comparable to those obtained by an established amperometric-titration method.

Experiments such as the 2XIIB experiment at Livermore have established the ability of mirror systems to confine high temperature, high density plasmas at central beta values exceeding unity. Given these results the next tasks for the mirror approach are to explore means for increasing the energy gain factor Q and to scale up the plasma volume, both of these requirements deriving from economic constraints. This report discusses means for increasng Q, including recent improvements in the tandem mirror concept and design studies of the field-reversed mirror in the context of upcoming and proposed scaled-up mirror experiments.

Progress is reported in research on the following subjects: gas chromatographic/mass spectrometric analysis of thermal degradation products from wood and composite burns; corrosion in the experimental ducting of the fire test cell; on-line x-ray fluorescence analysis of transition metals in waste water: Phase II; fire environmental tests for self-contained breathing apparatus; developments in neutron spectrometry; and, intermediate energy x-ray spectra for general shielding calculations. (JGB)

In conclusion, it may be stated that: Recycle processing of SRC-I coal extract produced an equilibrium recycle solvent containing 9 weight percent hydrogen after two recycle passes in the PDU; no refractory 850/sup 0/F+ material was detected when recycling 500/sup 0/F+ material; an 850/sup 0/F+ conversion of approximatly 87 weight percent (based on fresh SRC-I feed) was obtained during recycle processing at temperatures of 790 to 810/sup 0/F; a distillate product (390 to 850/sup 0/F) containing < 0.3 weight percent nitrogen was routinely obtained during recycle processing at the above noted high conversion; and in the recycle mode of processing coal extract at 780/sup 0/F, a catalyst addition rate of one pound of catalyst per ton of moisture-free coal gave an 850/sup 0/F+ conversion of 62 weight percent (based on fresh SRC-I feed) and a nitrogen content in the distillate fraction (390 to 850/sup 0/F) of 0.36 weight percent.

The second phase of a contract between the California Energy Commission and the G.R.I.P.S. Commission (Geothermal Research Information and Planning Services) is reported. The activities include: environmental studies; information exchange; funding proposals; and administration of GRIPS. (MHR)

A computer controlled ultrasonic scanning system and a data acquisition and analysis system have been developed to perform the inservice inspection of welds in stainless steel sodium piping in the Fast Flux Test Facility. The scanning equipment consists of a six axis motion mechanism and control system which allows full articulation of an ultrasonic transducer as it follows the circumferential pipe welds. The data acquisition and analysis system consists of high speed ultrasonic waveform digitizing equipment, dedicated processors to perform on-line analysis, and data storage and display equipment.

The intent of this design guide is to provide the engineer with the necessary information to produce a design for a workable installation. It contains a project scope, specific design information, and project control procedures. The desired process is to flash the geothermal brine to steam in three or four stages and transfer the steam heat energy to the working fluid circulating in closed loop. (MHR)

Using surface traces, scanning electron microscopy, and light microscopy, Ti-, Co-, Ni-, and Fe-base alloys were evaluated for erosion and stress corrosion cracking (SCC) after exposure at about 104{sup 0}C to the nozzle exhaust from acidified geothermal brine. Examples of erosion, SCC, and corrosion are shown. Results are evaluated in terms of synergism between erosion, corrosion, and stress. Repassivation kinetics might play a key role in the formation and growth of erosion cavities. Of the materials tested, the Ti-base alloys appear to have the best combination of resistance to SCC and erosion/corrosion in high-salinity, highly mineralized, acidified, two-phase nozzle exhaust.

The commercial development potential of 13 underdeveloped geothermal prospects in the Western United States has been examined and the prospects have been ranked in order of relative potential for development on the basis of investment considerations. The following were considered in the ranking: geotechnical and engineering data, energy market accessibility, administrative constraints, and environmental and socio-economic factors. The primary ranking criterion is the unit cost of energy production expected from each prospect. This criterion is obtained principally from expected reservoir temperatures and depths. Secondary criteria are administrative constraints, environmental factors and the quality of the geotechnical data. The Roosevelt, Utah, prospect ranks first in development potential followed in order by Beowawe, Nevada; Coso Hot Springs, California; Long Valley, California; and Brady's Hot Springs, Nevada.

Data on the properties of epoxy resin systems studied at Lawrence Livermore Laboratory have been collected and are presented in tabular form. Information is included on the chemical nature of the resins and curing agents, as well as data sheets for each system. Included in the data sheets are the composition of the system (resin, diluent, and curing agent); the cure schedule; tensile, compressive, and shear data; viscosity, gel time, and exotherm; density, shrinkage, and water absorption; the transition temperature; and thermal properties.

Background analyses of three control systems capable of controlling the speed, output voltage, and start rate of Brayton Isotope Power Systems (BIPS) are presented. Conclusions of all functions considered are summarized. (TFD)

During the report period, conceptual designs for the collector and steam generator subsystem research experiments (SREs) were approved, and design detailing began. The thermal storage SRE concept was modified through additional analyses and engineering model experiments and resubmitted for evaluation. Detailed designs for all three subsystems will be submitted during the next quarter. Preparation for SRE testing proceeded through procurement of long-leadtime items and detailed definition of test arrangements. Analysis and design of the electrical generation subsystem and balance of the plant proceeded essentially on schedule.

Progress in studying the cost and market potential of HSPF gas heat pumps of the 7/sup 1///sub 2/ ton and larger size level and in testing components of the system is reported. (LCL)

The design of the 2XII-B pulse coil system is presented. Development of the coil geometry is given as well as the results of magnetic field calculations. A discussion of the forces developed by this high-energy coil set and the electrical stress on the magnet insulation is presented. The results of materials selection for both the coil insulation and structure are included, and also a description of the fabrication procedure. (auth)

Recent efforts in controlled fusion experiments have indicated the need for large neutral-beam sources to provide an initial plasma for further plasma buildup, for use as a stoking source to makeup losses, or for plasma heating. Experiments now operating or envisioned for the near future anticipate the need for kilo-amp neutral beams in the 20-keV energy range and higher. These sources will be required to focus into relatively small-volume targets, have good gas efficiency, and use a minimum of excess gas for downstream neutralization. A test facility with sufficient pumping capacity to handle sources of this size is described. The ion source, mockup extraction grid, and the requisite electronic and power equipment for a 200-amp neutral-deuterium beam are discussed. The beam pulse length will be from 2 to 10 msec. (auth)

A review is given of the 2X project, including project history and recent results, with the intent that both those new to CTR engineering and those people familiar with its progress will benefit. The current 2XII Program plan is reviewed, with emphasis on the major device fabrication underway at the present time. This construction consists primarily of a new magnet for 2XII, and has been designated 2XIIB. The injection of a 800-A neutral beam is described. The final portion of the paper is a progress report and a summary of cost estimates and scheduling. (auth)

Both mirror machines at LLL, Baseball II and 2XII, require neutral-beam injection of hydrogen or deuteriurm into the plasma. The neutral-beam injector components and their function in the injector system are outlined. Some of the problems with the ion sources, neutralizers, magnetic shielding, beam burial, and vacuum pumping are discussed. (auth)

From fifth sympoaium on engineering problems of fusion research; Princeton, New Jersey, USA (6 Nov 1973). A review is given of the 2X project, including project history and recent results, with the irtent that both those new to controlled thermonuclear research engineering and those people familiar with its progress will benefit. The current 2XII program plan is reviewed, with emphasis on the major device fubrication underway at the present time. This construction consiats primarily of a new magnet for 2XII, and has been designated 2XIIB. The injection of a 600A neutral beam is described. The ftnal portion of the paper is a progress report and a summary of cost estimates and scheduling. (MOW)

A vacuum pumping system that provides a cryo surface for condensing and freezing of H/sub 2/ gas is described. A closed-loop vacuum system was designed and built at Lawrence Livermore Laboratory to pump down the neutralizer LH/sub e/ dewar with a volurae of 350 l and the lambda point dewar with a LH/sub e/ volume of 250 l. Both of these dewars can be pumped down simultaneously or one at a time. 100% of the H/sub e/ gas is recovered free of contaminations. The vacuum pump can handle 340 SCFM of gas. The LH/sub e/ dewars are pumped down below the lambda point. This condition reduces the LH/sub e/ container wall temperature to 2.1 deg K giving a base pressure of 10/sup -13/ torr for H/sub 2/ gas/sup 2/. To attain a stable condition the LH /sub e/ baths are puuped down to 33 torr or lower to give a surface temperatare of about 2/sup 0/K/sup 3/. The Baseball II helium factlity is a close loop system. The H/sub e/ gas is recovered from all the LH/sub e/ usage point. This gas is accumulated in one of the two 8000 cu ft inflatable gas bags. The gas from the gas …