The Sunkist Citrus Plant in Ontario, California, processes about 6 million pounds of citrus fruit per day to make products which include frozen concentrated juice; chilled, pasteurized, natural strength juice; molasses from peel; dried meal from peel; pectin; citrus oil; and bioflavonoids. The energy intensive operations at the plant include concentration, drying, and refrigeration. The objective of the two-year two-phase project is to identify an economically viable alternative to the existing method of meeting energy requirements. Progress on the technical work of Phase I is reported. The following are summarized: requirements (energy price projection, atmospheric emission requirements, citrus juice quality constraints, economic evaluations); characterization (basic citrus processing operations, energy consumption and fruit processed vs time, identification and measurement of energy uses, energy balance for a typical citrus juice evaporator); and thermodynamic analysis (heat pump model, thermal evaporator, and co-generation model).

Absorption spectra obtained from SmBr/sub 3/, SmBr/sub 2/, and Sm0Br were used in identifying the samarium species in several mixed-valence Sm(II/III) compounds produced by H/sub 2/ reduction of SmBr/sub 3/. The nature of the absorption of Sm0Br made it possible to detect even traces of Sm0Br in the Sm bromides.

The rates for a number of reactions producing certain stable nuclides, such as /sup 3/He and /sup 4/He, and fission in the moon are calculated for galactic-cosmic-ray particles and for solar protons. Solar-proton-induced reactions with bromine usually are not an important source of cosmogenic Kr isotopes. The /sup 130/Ba(n,p) reaction cannot account for the undercalculation of /sup 130/Xe production rates. Calculated production rates of /sup 15/N, /sup 13/C, and /sup 2/H agree fairly well with rates inferred from measured excesses of these isotopes in samples with long exposure ages. Cosmic-ray-induced fission of U and Th can produce significant amounts of fission tracks and of /sup 86/Kr, /sup 134/Xe, and /sup 136/Xe, especially in samples with long exposures to cosmic-ray particles.

The method is based on counting the 186-keV gamma rays emitted by /sup 235/U using a Pb-collimated Ge(Li) detector. Measurements of fifty UF/sub 6/ product and feed cylinders reveal the following precisions and counting times: Product - 2S, 0.98% (600 s); Feed - 2S, 0.48% (2500 s); Product - 1S, 0.62% (1000 s); Feed - 1S, 0.73% (3000 s). A 1% precision is desired for variables - attributes verification measurements of /sup 235/U assay in UF/sub 6/ sample cylinders for safeguards inspections by the International Atomic Energy Agency (IAEA). Statistically, these measurements stand between fine, high-precision (or variables) measurements and gross, low-precision (or attributes) ones. Because of their intermediate precisions, the variables-attributes measurements may not require analysis of all samples, and this could result in significant savings of IAEA inspector time. Although the precision of the above results is satisfactory, the average relative differences between gamma-ray and mass-spectrometric determinations for the last two sets of measurements (1S cylinders) have positive biases.

The focus is on electric power production using geothermal resources greater than 150/sup 0/C because this form of geothermal energy utilization has the most serious health-related consequences. Based on measurements and experience at existing geothermal power plants, atmospheric emissions of noncondensing gases such as hydrogen sulfide and benzene pose the greatest hazards to public health. Surface and ground waters contaminated by discharges of spent geothermal fluids constitute another health hazard. It is shown that hydrogen sulfide emissions from most geothermal power plants are apt to cause odor annoyances among members of the exposed public - some of whom can detect this gas at concentrations as low as 0.002 parts per million by volume. A risk assessment model is used to estimate the lifetime risk of incurring leukemia from atmospheric benzene caused by 2000 MW(e) of geothermal development in California's Imperial Valley. The risk of skin cancer due to the ingestion of river water in New Zealand that is contaminated by waste geothermal fluids containing arsenic is also assessed. Finally, data on the occurrence of occupational disease in the geothermal industry are summarized briefly.

"Results of a reconnaissance geochemical survey are reported for the Milbank Quadrangle, Minnesota; North Dakota; South Dakota. Statistical data and areal distributions for uranium and uranium-related variables are presented for 662 groundwater and 319 stream sediment samples. Also included is a brief discussion on location and geologic setting." (from Abstract)

A multiple-reflection optical cell for Raman or fluorescence gas analysis consists of two spherical mirrors positioned transverse to a multiple-pass laser cell in a confronting plane-parallel alignment. The two mirrors are of equal diameter but possess different radii of curvature. The spacing between the mirrors is uniform and less than half of the radius of curvature of either mirror. The mirror of greater curvature possesses a small circular portal in its center which is the effective point source for conventional Fl double lens collection optics of a monochromator-detection system. Gas to be analyzed is flowed into the cell and irradiated by a multiply-reflected composite laser beam centered between the mirrors of the cell. Raman or fluorescence radiation originating from a large volume within the cell is: (1) collected via multiple reflections with the cell mirrors; (2) partially collimated; and (3) directed through the cell portal in a geometric array compatible with Fl collection optics.

A new electric gun system was constructed for use in high-pressure EOS studies. The system is powered by a 100 kV, 15.6 ..mu..F capacitor bank. At 100 kV charging voltage the system inductance is 23 nH. This system has driven 0.3 mm-thick Kapton projectiles to > 20 km/s and 0.3 mm Kapton/30 ..mu..m Ta projectiles to approx. 10 km/s. Projectile velocity is modeled phenomenlogically by an electrical Gurney model.

A heat-exchanging fireplace was installed in a 2000 square foot home and the standard air distribution equipment was ducted directly to the forced-air heating system of the home. The standard air distribution equipment for the fireplace included two squirrel-cage blowers which were connected to a thermostat, allowing a choice of temperature ranges; and a snap disc thermostat was used to disconnect the blowers in order to avoid blowing cold air after the fire died out. Arranged in this manner, one is able to set the regular home thermostat a few degrees lower than the fireplace thermostat, and this will allow the regular heating system to turn on after the fire has gone out in the fireplace. Energy consumption in both the fireplace and the conventional heating system was monitored throughout a heating season and then compared with past heating seasons when only a conventional heating system was used.

The interferometer and viewing optics that are the main optical components of an Automated Surface Mapping system (ASM) used to characterize the surface topography and the wall thickness uniformity of opaque and transparent spherical shells is described. To characterize surface finish or wall thickness of spherical shells with an accuracy of 10 nm and a resolution of 1 ..mu..m the differential phase shift between two beams of orthogonal polarizations is measured, before and after the probe beam has interacted with the test object.

The following are included in the well test plan: well test program schedule and order of work; the injection well drilling program details; the production well drilling program details; and long-term (30-day) production testing program details. (MHR)

Work covered in this report includes the activities associated with the status of the simulated reactor helium supply systems and testing equipment. The progress in the screening test program is descibed; this includes: screening creep results and metallographic analysis for materials thermally exposed or tested at 750/sup 0/, 850/sup 0/, 950/sup 0/ and 1050/sup 0/C (1382/sup 0/, 1562/sup 0/, 1742/sup 0/, and 1922/sup 0/F) in controlled-purity helium. The status of creep-rupture in controlled-purity helium and air and fatigue testing in the controlled-purity helium in the intensive screening test program is discussed. The results of metallographic studies of screening alloys exposed in controlled-purity helium for 3000 hours at 750/sup 0/C and 5500 hours at 950/sup 0/C, 3000 hours at 1050/sup 0/C and 6000 hours at 1050/sup 0/C and for weldments exposed in controlled-purity helium for 6000 hours at 750/sup 0/C and 6000 hours at 1050/sup 0/C are presented and discussed.

In neutron dosimetry, calculations enable one to predict the response of a proposed dosimeter before effort is expended to design and fabricate the neutron instrument or dosimeter. The nature of these calculations requires the use of computer programs that implement mathematical models representing the transport of radiation through attenuating media. Numerical, and in some cases analytical, solutions of these models can be obtained by one of several calculational techniques. All of these techniques are either approximate solutions to the well-known Boltzmann equation or are based on kernels obtained from solutions to the equation. The Boltzmann equation is a precise mathematical description of neutron behavior in terms of position, energy, direction, and time. The solution of the transport equation represents the average value of the particle flux density. Integral forms of the transport equation are generally regarded as the formal basis for the Monte Carlo method, the results of which can in principle be made to approach the exact solution. This paper focuses on the Monte Carlo technique.

JANUS, a two-sided, interactive wargame simulation code, was used to explore how using each of several different yield options in a nuclear artillery shell might affect a tactical battlefield simulation. In a general sense, the results or outcomes of these simulations support the results or outcomes of previous studies. In these simulations the Red player knew of the anticipated nuclear capability of the Blue player. Neither side experienced a decisive win over the other, and both continued fighting and experienced losses that, under most historical circumstances, would have been termed unacceptable - that is, something else would have happened (the attack would have been called off). During play, each side had only fragmentary knowledge of the remaining resources on the other side - thus each side desired to continue fighting on the basis of known information. We found that the anticipated use of nuclear weapons by either side affects the character of a game significantly and that, if the employment of nuclear weapons is to have a decided effect on the progress and outcome of a battle, each side will have to have an adequate number of nuclear weapons. In almost all the simulations we ran using JANUS, enhanced radiation …

A weekly publication, the Texas Register serves as the journal of state agency rulemaking for Texas. Information published in the Texas Register includes proposed, adopted, withdrawn and emergency rule actions, notices of state agency review of agency rules, governor's appointments, attorney general opinions, and miscellaneous documents such as requests for proposals. After adoption, these rulemaking actions are codified into the Texas Administrative Code.

This report is about perceptions of national energy problem

The report from Lawrence Livermore National Laboratory, which covers the period from October 1981 to September 1982, is divided into three major sections. The first section, progress reports, includes studies in areas of industrial hygiene, instrument development, environmental protection, radiation protection and fire safety. The second section, technical notes, contains reports on interesting activities of a more limited scope. The third section lists recent publications. (JMT)

To quantify the potential for {sup 129}I to migrate from buried waste at the Savannah River Plant (SRP) burial ground, a four year study was made. Spent berl saddles containing 68.7 mCi of {sup 129}I from separations process air filters were buried in a 10 ft. {times} 10 ft. {times} 12 ft. deep lysimeter exposed to normal weather conditions at the burial ground. During the four year study leaching and migration released 48.5 nCi of {sup 129}I from the 68.7 mCi buried in the lysimeter. This represents an average 1.77 {times} 10{sup {minus}7} fraction/year released. The release rate was relatively constant during the four years, varying mainly with seasonal rainfall. Calculations based on these results indicate a release of <3 {mu}Ci/year of {sup 129}I from SRP buried waste to the groundwater. Qualitatively this release and subsequent migration has recently been confirmed by measurement of 0.25 pCi {sup 129}I /1 in water from a well 600{prime} southwest of the burial ground.

Plutonium fueled radioisotopic heat sources find space, terrestrial, and undersea applications to generate electrical power. Such systems under postulated accident conditions could release radioactivity into the environment resulting in risks to the general population in the form of radiological doses and associated health effects. The evaluation of the radiological impact of postulated scenarios involving releases of activity into the environment includes identification of postulated accident release modes, including the probability of release and the release location; source term definition, including the activity of each radionuclide released and the corresponding chemical form and particle size distribution; analysis of the environmental behavior of the released radioactivity to determine the concentrations in environmental media (air, soil, and water) as a function of time; and analysis of the interaction between the environmental concentrations and man, leading to ingestion, inhalation, and external doses through each environmental exposure pathway. 443 refs., 2 figs., 4 tabs.

Plutonium-fueled radioisotopic heat sources find application in a spectrum of space, terrestrial, and underseas applications to generate electrical power by thermoelectric or dynamic-cycle conversion. Such systems under postulated accident conditions could release radioactivity into the environment resulting in risks to the general population. The released radioactivity could be dispersed into various environmental media, such as air, soil, and water and interact with people through various exposure pathways leading to inhalation, ingestion, and external radiological doses and associated health effects. The authors developed short-term exposure (RISK II) and long-term exposure (RISK III) models for use in safety risk assessments of space missions utilizing plutonium-fueled electric power systems. To effectively use these models in risk assessments, representative input values must be selected for a spectrum of environmental transfer parameters that characterize the behavior of plutonium in the environment. The selection of appropriate transfer parameters to be used in a given analysis will depend on the accident scenarios to be modeled and the terrestrial and aquatic environments to be encountered. The authors reviewed the availability of plutonium in the environment. This report summarizes the research programs presently being conducted at six Department of Energy Laboratories and makes recommendations on areas where further research …

Results pertaining to the recently modified beam-injection arrangement in the central cell of TMX-U are presented here. These modifications followed our observation that beam atoms injected perpendicular to the magnetic axis between the first two magnet-coil gaps give rise to trapped ions with midplane pitch angles lying in the intervals 68/sup 0/ < theta < 78/sup 0/ and 59/sup 0/ < theta < 65/sup 0/. These pitch-angle intervals are similar in value to the earlier arrangement of beams injected at the midplane at pitch angles of 58 and 70/sup 0/. Normal injection at an off-midplane position has two advantages when compared with off-normal injection at the midplane. First, the unattenuated beam can be dumped in the first-injector region rather than in the plasma region. Second, the beams can be oriented with their long dimension horizontal rather than vertical. The first point al

This report describes calculations and analysis performed in an attempt to provide a new estimate for the yield of the Hiroshima weapon. Newly discovered meteorological data was adapted for use in one- and two-dimensional hydrodynamic codes, and a series of calculations was then run for different values of yield. The objective was to determine what yield produced an overpressure record which could best be correlated with an actual trace measured at a parachute-dropped canister. Altitude of the bomb and canister-carrying aircraft at drop time was also a variable parameter. The analysis provides an estimate of 16.6 + 0.3 kt for the yield of the Hiroshima weapon. A drop altitude of near 35,500 feet is shown to be consistent with the signal time-of-arrival. This yield value is within the range of other estimates, but the drop altitude is higher than that previously assumed to be reasonable.

The dissolution of plutonium dioxide in nitirc acid (HNO/sub 3/) at high hydrofluoric acid (HF) concentrations has been investigated. Dissolution rate curves were obtained using 12M HNO/sub 3/ and HF at concentrations varying from 0.05 to 1.0 molar. The dissolution rate increased with HF concentration up to 0.2M and then decreased at higher concentrations. There was very little plutonium dissolved at 0.7 and 1.0M HF because of the formation of insoluble PuF/sub 4/. Various oxidizing agents were added to 12M HNO/sub 3/-1M HF dissolvent to oxidize Pu(IV) to Pu(VI) and prevent the formation of PuF/sub 4/. Ceric (Ce(IV)) and silver (Ag(II)) ions were the most effective in dissolving PuO/sub 2/. Although these two oxidants greatly increased the dissolution rate, the rates were not as rapid as those obtained with 12M HNO/sub 3/-0.2M HF.

This subgroup has focussed on detectors for fixed target experiments which have full azimuthal coverage. The general scope of the working group was to consider (1) the configuration of an idealized detector, and (2) various configurations of practical detectors that could be implemented on a relatively short time scale. The second category includes possible upgrades and modifications of existing experimental facilities. Beams of both 15 GeV/A sulphur at the AGS and 200 GeV/A oxygen at the SPS were considered.