The 10-cm (grid diameter) duoPIGatron ion source produces pulsed hydrogen ion beams of 10 to 15 A beam current in the 20- to 40-keV energy range for a duration of a few tenths of a second. To fulfill the requirements of the next generation of high-power neutral beam injectors for heating plasmas in CTR devices, this source has been enlarged to a version 15-cm in grid diameter. In addition, by utilizing a magnetic multipole line cusp field confinement method, the plasma created is characterized over the 15 cm grid diameter by a noise level within +- 10 percent and spatial density variations within +- 15 percent at a density on the order of 10/sup 12/ cm/sup -3/. This larger source has operated reliably and produced a beam current exceeding 30 A of hydrogen at 27 keV. Initial operation of a 20-cm version of this source employing line cusp confinement has produced an extraction current of 60 A at 33 keV.

Of the various possible unconventional natural gas resources that have been examined, the most recent, and by far the largest, is that which is dissolved in the hot salt water within the geopressurized zones of the Gulf Coast. Recent assessments have estimated that the amount of gas contained in these waters, underlying about 150,000 sq. mi. of Texas and Louisiana--both onshore and offshore--is between 60,000 and 100,000 quads. In addition to the natural gas, there is a huge potential for producing electric power from the heat content of the fluid, as well as other potential uses for hot water. The net value of this geothermal heat may be about half that of the natural gas. The major problems associated with commercial production of the fluids from these zones and the extraction of energy from the heat and pressure of the fluid are discussed and the long-term potential is estimated. It appears likely that commercial production will depend upon the existence of uncontrolled prices for natural gas and the satisfactory resolution of various legal, environmental, and institutional problems, all of which are likely to require considerable effort. Although the production potential from the Gulf Coast zones might be accurately estimated after …

A Faraday cup design for a 1 mA.cm/sup -2/ 100-keV, light-ion-beam measurement in background plasma is proposed. Features of this shielded, three-grid structure with deep target are described, and a mechanical draft is included. In the appendix, we reference and survey results of experiments reporting the number and energy range of secondary electrons and back-scattered ions originating on various metal surfaces bombarded with approximately 100-keV hydrogen and deuterium ions. Choice of target and grid materials in cup assembly follow from this survey.

The faciliies described will provide a direct route from the 241-S-151 and 241-U-151 Diversion Boxes to the 241-SY Tanks. The 244-S Catch Station will consist of a 20,000 gallon primary tank contained within a concrete vault lined with carbon steel. Encased three-inch carbon steel process lines will be extended to the catch station pump pit from the 241-SY Tank Farm, the 241-S-151 Diversion Box and the 241-U-151 Diversion Box encasement. The facility will have its own ventilation system for exhausting the primary tank and the annulus area. A small instrument shack will house locally mounted instrumentation and controls. Existing designs for Project B-103 will be used where similarities exist (H-2-38200). The project is expected to cost $1,900,000 and require 19 months for the initiation of Title I design until construction is complete.

The parametric decay of an electromagnetic wave into two electron plasma waves is considered. The electromagnetic wave is obliquely incident on the density gradient. The resulting analysis shows that the threshold for absolute instability decreases as the angle of incidence of the electromagnetic wave relative to the density gradient approaches 90/sup 0/. The importance of this result to laser fusion is discussed.

A proposed accelerator safety standard for the Lawrence Livermore Laboratory (LLL) is given. All accelerators will comply with this standard when it is included in the LLL Health and Safety Manual. The radiation alarm and radiation safety system for a radiography facility are also described.

Research progress on the LX-07 physics design for the two-stage shape charge is reported. (TFD)

Experiments were performed in an attempt to make thin n/sup +/ contacts on high-purity germanium by the solid phase/sup 1)/ epitaxial regrowth of arsenic doped amorphous germanium. After cleaning the crystal surface with argon sputtering and trying many combinations of layers, it was not found possible to induce recrystallization below 400/sup 0/C. However, it was found that simple thermally evaporated amorphous Ge made fairly good electron or hole blocking contacts. Excellent spectrometers have been made with amorphous Ge replacing the n/sup +/ contact. As presently produced, the amorphous Ge contact diodes show a large variation in high-voltage leakage current.

An investigation was conducted of malfunctions of snubbers (seismic-shock arrestors) in service in nuclear power plants. The construction and use of snubbers is summarized, and the history of snubber problems in nuclear service is reviewed. Reports of many hundreds of snubber malfunctions were found in the abnormal-occurrence reports of the docket literature. The great majority of these abnormal occurrences consisted of hydraulic snubbers whose hydraulic fluid had leaked out because of deteriorated seals; snubbers that were damaged in manufacture, shipping, installation, refitting, or use; and snubbers whose performance did not match service requirements. Additional information about the failures was obtained from the reactor operators, snubber manufacturers, reactor vendors, and independent laboratories. The abnormal occurrences were classified into 12 categories. Analyses of the causes of the individual abnormalities are presented, and preliminary comments on the current state of snubber manufacture and use are made.

An event tree is developed, outlining ways which radioactivity can be accidentally released from high level solidified wastes. Probabilities are assigned to appropriate events in the tree and the major contributors to dose to the general population are identified. All doses are computed on a per megawatt electric-year basis. Sensitivity relations between the expected dose and key characteristics of the solidified wasted are developed.

Analyses of experiments in the initial critical assemblies for the gas-cooled fast breeder reactor (GCFR) were conducted using the calculational methods at General Atomic (GA) for GCFR design. The assemblies, constructed on the ZPR-9 facility at Argonne National Laboratory, simulated features of the 300-MW(e) GCFR demonstration reactor. Studies relating to the safety of this reactor design and to the GCFR concept in general were concerned with (1) reactivity coefficients of fuel and poison materials to evaluate loading and control requirements, (2) the worth of helium coolant in a depressurization event, (3) the Doppler effect in uranium to determine power coefficients, and (4) the effect of hypothesized steam ingress into coolant channels as a potential for reactivity addition and altering core neutronic and control characteristics. Results are reported for GA analyses of such safety-related physics measurements in two basic assemblies, the 3150-liter phase I core with a coolant void fraction of 55% and the 1300-liter phase II core with a 45% void fraction.

An analysis of the fabrication and field test requirements for a drilling machine that would be applicable to the drilling of large diameter holes for the emplacement of radioactive waste canisters in an underground repository is presented. On the basis of a previous study in 1975 by RE/SPEC Inc. for the Oak Ridge National Laboratory, it was concluded that none of the commercially available machines were ideally suited for the desired drilling application, and that it was doubtful whether a machine with the required capabilities would become available as a standard equipment item. The results of the current study, as presented here, provide a definitive basis for selecting the desired specifications, estimating the design, fabrication, and testing costs, and analyzing the cost-benefit characteristics of a custom-designed drilling machine for the emplacement hole drilling task.

The analytical methods developed or adopted for use in support of radiochemistry and gamma ray spectroscopy, HTGR fuel reprocessing, HTGR fuel development, TRIGA fuel fabrication, and miscellaneous projects are reported. (JSR)

The electron-phonon interaction in aluminum was studied using Fermi-surface-fitted 4-OPW electron states, a realistic phonon spectrum, and integration mesh-density varying with local Fermi surface curvature. The resulting electron mass enhancement lambda and thermal scattering rate tau/sup -1/ are evaluated as functions of position on the Fermi surface. It was found that the agreement between observed and calculated cyclotron masses is improved by the use of an anisotropic effective mass enhancement (lambda) rather than the average one. The anisotropy of lambda is determined predominantly by mixing coefficient variations, rather than by phonon anisotropy. The scattering rate tau/sup -1/ exhibits order-of-magnitude variations over the Fermi surface at low temperatures. Its values at 5/sup 0/K are within 50% of the experimentally observed ones everywhere, with better agreement in free-electron regions. In free-electron regions, umklapp processes cause a more rapid increase than T/sup 3/ for temperatures above 15 to 25/sup 0/K. On ridges, where the initial T/sup 3/-coefficient is very large, a slower increase is found. There results a washingout of anisotropy with increasing temperature. The results on lambda are in good agreement with those of a recent similar calculation; the tau/sup -1/ results agree qualitatively but not quantitatively.

Initial analytical and experimental investigations were conducted to establish data and design procedures prior to a demonstration of the Annual Cycle Energy System (ACES) in an actual building. ACES is an integrated system for supplying space heating and cooling, and domestic hot water to a building through the use of a heat pump, a thermal storage unit, and an outdoor radiative/convective panel. The heat pump extracts energy from a tank of stored water to provide winter heating. The ice that is formed is accumulated for subsequent use in meeting the cooling requirements of the building in the summer. A components test assembly was constructed to measure the rates of heat transfer during ice buildup and brine chilling operations, to assess the design requirements of the evaporator and the desuperheater for producing domestic hot water using refrigerant superheat, and to investigate the mechanical stability characteristics of the ACES freezing coils which are submerged in the water storage tank. The findings of the experimental program are presented and analytical methods for optimally sizing system components according to the thermal characteristics of a building and the climatic zone where it is located are developed. The calculation of the annual coefficient of performance for …

Monsanto Research Corporation operates Mound Laboratory, a government-owned facility of the U.S. Energy Research and Development Administration, at Miamisburg, Ohio. Mound Laboratory is an integrated, research, development, and production facility performing work in support of ERDA weapon and nonweapon programs with emphasis on explosive and nuclear technology. Mound Laboratory originated as a technical organization in 1943 when Monsanto Chemical Company was requested to accept responsibility for determining the chemical and metallurgical properties of polonium as a project of the Manhattan Engineering District. Work was carried on at Monsanto`s Central Research Department and several satellite units in the Dayton, Ohio area. Late in 1945, the Manhattan Engineering District determined that the research, development and production organization established by Monsanto at Dayton should become a permanent facility. A search for a suitable location in early 1946 led to the selection of a 180-acre tract adjacent to Miamisburg, about ten miles (16 km) south of Dayton. Construction of Mound Laboratory, which was named after the Miamisburg Indian Mound adjacent to the site, began in February 1947 and was completed in 1948. The new laboratory was the first permanent facility of the Atomic Energy Commission which had succeeded the Manhattan Engineering District.

Offsite radioactivity releases in the Clinch River are less than 1 percent of the amount allowable for unrestricted use of the water. However, studies were conducted on the radioactivity contributions to the Clinch River from the buried waste at ORNL and on implementing corrective measures. The /sup 60/Co-organic complexes present in ground water near trench 7 are present in two molecular weight fractions, one greater than 700 and one less than 700, with 85 percent of the /sup 60/Co being transported with the lighter fraction. The chemical composition of this fraction may be composed of natural organics or EDTA. The calculated discharge of /sup 90/Sr from burial ground 4 to White Oak Creek showed a decrease in the discharge corresponding to a decrease in precipitation. The calculated discharge does not agree with stream-monitoring data, and it is believed that the stream-monitoring data are in error or that a new source of /sup 90/Sr is present in the drainage. Drainage improvements for the burial ground have been installed. Alpha radioactivity was found in water samples from burial ground 5, and the water from one seep had both /sup 244/Cm and /sup 238/Pu. Corrective measures were applied to reduce the amount of …

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A direct-electrical-heating apparatus has been built to simulate in-reactor temperature gradients and heating conditions in both the mixed nitrides and carbides of uranium and plutonium. The apparatus has the capability for the investigation and direct observation of fuel-behavior phenomena that should significantly enlarge the data base on mixed carbides and nitrides at temperatures near and above their melting points. In addition to heating UC, results of prooftests showed that the apparatus has the capability to heat graphite, 30 vol % ZrC in graphite, B/sub 4/C control-rod pellets, and stainless steel.

Tabulated data are presented on the content of /sup 90/Sr and /sup 89/Sr in fallout deposited at various world land sites; /sup 90/Sr in milk and drinking water samples from various locations; and the content of Pb in samples of surface air. (CH)

Hastelloy X, an Ni--Cr--Fe--Mo alloy, may be an important structural alloy for components of gas-cooled reactor systems. Expected applications of this alloy in the High-Temperature Gas-Cooled Reactor (HTGR) are discussed, and the development of interim mechanical properties and supporting data are reported. Properties of concern include tensile, creep, creep-rupture, fatigue, creep-fatigue interaction, subcritical crack growth, thermal stability, and the influence of helium environments with controlled amounts of impurities on these properties. In order to develop these properties in helium environments that are expected to be prototypic of HTGR operating conditions, it was necessary to construct special environmental test systems. Details of construction and operating parameters are described. Interim results from tests designed to determine the above properties are presented. To date a fairly extensive amount of information has been generated on this material at Oak Ridge National Laboratory and elsewhere concerning behavior in air, which is reviewed. However, only limited data are available from tests conducted in helium. Comparisons of the fatigue and subcritical growth behavior in air between Hastelloy X and a number of other structural alloys are given.

A discussion is provided of the following aspects of the solar process hot water program: criteria and rationale used in process selection, expected fuel savings to be provided by widespread use of the solar energy system in the industry, and economic evaluation of the system. The design, construction, operation, and evaluation of a solar water heating system for application to the can washing process at the Campbell Soup Company's plant located in Sacramento, California are included.

The design and performance of a solar hot water system for can washing at the Campbell Soup Plant in Sacramento, California, are presented. The collector field is located on the roof of the finished products warehouse of the Campbell Soup Sacramento plant. Water is supplied from a 3.8 cm (1/sup 1///sub 2/ in.) supply line which is located directly below an existing roof access hatch. A supply pipe will be brought up through that hatch. The water flow will then be split into two manifold lines which supply the dual rows of flat plate collectors. The preheated water from the flat plates is then passed into six sets of parallel connected concentrators. Each set consist of eight 1.83 x 3.05 m (6 x 10 foot) modules connected in series. The water from these units is gathered in a 3.8 cm (1/sup 1///sub 2/ in.) insulated pipe which transports it to the storage tank. This pipe will be attached to an existing pipe run until it reaches the can washing building. From there the pipe will follow the can washing building around to the storage tank. The storage tank is a 75,200 1 (20,000 gal) steel tank which is coated internally …

ARGUS is a two-beam Nd: glass laser system built for laser fusion irradiation experiments. It is the first glass laser system planned and built with the understanding that small-scale beam break-up is the dominant performance limiting factor in obtaining high output power. Accordingly, five vacuum spatial filters are located at strategic intervals along each chain to eliminate the accumulated small-scale filamentation. This strategy permits cascading of amplifiers to obtain a focusable output of more than one terawatt per arm in a spatially clean beam of 20 centimeter diameter. Beam diagnostics which characterize each shot include the time-integrated spatial profile and the time resolved intensity/power at the target. Demonstrated performance to date includes: (1) Peak power in excess of 2 TW at the target is achieved with regularity. (2) Maximum system brightness is in excess of 10/sup 17/ watts/cm/sup 2/ ster. (3) Shot-to-shot pointing stability within 50 ..mu.. radians is achieved over periods of days. (4) Successful target experiments have been performed with pulses of from 30 to 500 ps duration.