The relatively low temperature of thermal discharges from steam-electric power plants makes waste-heat utilization difficult without modification of the power cycle and attendant reduction in electrical-energy generating efficiency. The in-situ beneficial use of waste heat by direct once-through condenser discharge into a municipal water supply is discussed. Computations are presented regarding the matching of flow rates, heat losses in distribution and energy savings. A number of benefits and penalties are also assessed qualitatively including legal and operational aspects and reliability. Especially attractive are improvements in generating efficiency, alleviation of water-pipe freeze up, savings in water-heater energy, and improvement in wastewater treatment effectivness. Disadvantages include the need for careful control of condenser water quality and the question of public acceptance of water heated by about 13/sup 0/C. Two cases with operating experience are briefly discussed, although the installations were not developed for energy conservation purposes.

Ion-backscattering, ion-channeling, and transmission electron microscopy (TEM) were used to study a series of ion implanted silicon samples that were annealed with either a pulsed laser or a pulsed electron beam. Single crystal ((001) orientation) silicon samples were implanted with either 35 or 100 keV /sup 75/As/sup +/ to a dose of approx. 1 x 10/sup 16/ As/cm/sup 2/ and subsequently annealed with either a Q-switched pulsed Ruby laser or the electron beam generator. A series of energy densities was used in both cases to optimize results. It was determined from backscattering that the as-implanted profiles were redistributed in essentially the same manner for both types of anneals, indicating that melting and rapid recrystallization has occurred. For the 35 keV /sup 75/As/sup +/ implanted samples the two techniques produced equivalent anneals with no remaining damage as indicated by channeling and TEM. However, for the 100 keV implants the anneal was not uniform across the sample in the electron beam case and the channeling minimum yields for the major axes ((110), (111), and (100)) were higher than the laser annealed results. In both cases, the As substitutionality (97 to 99%) and minimum yields are better than results obtained from conventional thermal …

Radiation fields created by the production of /sup 7/Be in lithium of the Fusion Materials Irradiation Test (FMIT) Facility can be sufficiently high to prevent contact maintenance of system components. Preliminary experiments have shown that /sup 7/Be will adhere strongly to the FMIT piping and components and a good control method for /sup 7/Be must be developed. The initial experiments have been conducted in static stainless steel capsules and a Modified Thermal Convection Loop (MTCL). The average lithium film thickness on stainless steel was found to be 11 ..mu..m in the temperature range 495/sup 0/ to 571/sup 0/K from the capsule experiments. The diffusion coefficient for /sup 7/Be in stainless steel at 543/sup 0/K was calculated to be 5.31 x 10/sup -15/ cm/sup 2//sec. The cold leg of the MTCL picked up much of the /sup 7/Be activity released into the loop. The diffusion trap, located in the cold leg of the MTCL, was ineffective in removing /sup 7/Be from lithium, at the very slow flow rates (< 3.79 x 10/sup -4/ m/sup 3//s) used in the MTCL. Pure iron has been shown to be superior to coblat and nickel as a getter material for /sup 7/Be.

The purpose of this investigation was to determine the corrosion behavior of a high strength steel (ASTM A416-74 grade 270), typical of those used as tensioning tendons in prestressed concrete pressure vessels, in several corrosive environments and to demonstrate the protection afforded by coating the steel with either of two commercial petroleum-base greases or Portland Cement grout. In addition, the few reported incidents of prestressing steel failures in concrete pressure vessels used for containment of nuclear reactors are reviewed. The susceptibility of the steel to stress corrosion cracking and hydrogen embrittlement and its general corrosion rate were determined in several salt solutions. Wires coated with the greases and grout were soaked for long periods in the same solutions and changes in their mechanical properties were subsequently determined. All three coatings appeared to give essentially complete protection but small flaws in the grease coatings were detrimental; flaws or cracks less than 1 mm wide in the grout were without effect.

After a brief review of the origin of the radiation according to the standard model, the status of present measurements of the spectrum and the large-scale isotropy is discussed. Finally, it is indicated what are the prospects for improved measurements in the next decade. 17 references. (JFP)

A study of the signal physics of magnetic anomaly detection was carried out by superconducting gradiometer and magnetometer loop systems with SQUID sensors for possible application to the LASL geothermal energy program. In particular, the crack produced by hydrofracture of a deep HDR geothermal borehole would be filled with a magnetic material such as ferrofluid. When polarized by the earth's field, this material would produce a localized crack magnetic anomaly which is characteristic of the azimuth of the vertical crack with respect to magnetic north. Signatures of the anomaly would be determined by taking rotation data before and after filling the crack with magnetic material. A mathematical description was found for these signatures. To test the theory and the feasibility of the idea, the deep borehole vertical cracks were simulated by using panels to define sheets 1.5 mm thick, 1.2 m wide, and 2.5 m high. When filled with ferrofluid of suitable magnetic permeability, the local anomaly develops. Signatures were measured with a horizontal axial gradiometer rotated about a vertical axis. Good agreement was found between theory and experiment for aximuths in the east and west quadrants but only fair agreement in the north and south quadrants.

Electron microscopy and x-ray techniques have been used to investigate dislocation generation, precipitation of dopants and intrinsic defects, and the relaxation of unidirectional strains after thermal annealing of boron implanted, laser annealed silicon. It is shown that the number density of dislocations created near the interface after thermal annealing is small and therefore the unidirectional nature of the contraction in the dopes layer is essentially retained. A small number density of defect clusters (mostly vacancy dislocation loops, average size 20A) was also observed after thermal annealing at 1000/sup 0/C. Boron depth profile changes, as determined by secondary ion mass spectroscopy, indicated an increase in boron concentration near the surface in addition to the expected broadening of profiles after thermal annealing.

The results of an investigation into the effects of geometric stress concentrations on the elevated-temperature low-cycle fatigue behavior of Type 304 stainless steel are presented. The objective of this study was to develop a data base that could be used to verify the ASME Code Case 1592-8 design method for predicting the creep-fatigue behavior of structural components which contain discontinuities. In continuous-cycling tests, the local strains at the notch root determined from the Code Case procedure result in fatigue-life estimates that are conservative when compared to the experimental values. For tests containing a hold time at the peak tensile strain, the Code Case procedure results in local strains that are nearly identical to the experimentally obtained local strains, if the local stress is assumed to relax to the nominal value during the hold time.

A primary objective of the Tokamak Fusion Test Reactor Project (TFTR) is to demonstrate the production of fusion energy using the deuterium--tritium fusion reaction in a magnetically confined plasma system. This paper will discuss the various tritium control methods employed to minimize the release of tritium to the environment. The methods to be described include the containment and ALAP philosophy, engineered safety features, redundant tritium cleanup systems, redundant instrumentation and control systems, interlocks, monitoring systems, management controls, and waste handling systems. Estimates will be included concerning the impact of routine and accidental tritium releases with these control systems in place.

An attempt is reported to build self-consistent evolutionary models of complete massive stars, starting from their observable zero-age main sequence configurations, and evolving through their various hydrostatic nuclear burning stages, iron core collapse, bounce, outward-going shock formation, and finally, explosive nucleosynthesis and supernovae light curve formation. The model incorporates implicit hydrodynamics with a new treatment of time-dependent convection and semiconvection, and a careful treatment of the complexities of the advanced stages of stellar burning. The model was used to completely evolve population I stars of 15 and 25 M/sub solar mass/, with excellent agreement with the known properties and the prediction of other properties. 65 references. (JFP)

A method is presented which allows the determination of the role of helium on microstructural evolution in complex alloys and which avoids many of the problems associated with other simulation experiments. It involves a direct comparison of the materials' response to a primary difference in fission and fusion environments, namely the rate of helium generation. This is accomplished by irradiating specimens in a fission reactor and conducting microstructural analyses which concentrate on alloy matrix regions adjacent to precipitates rich in boron or nitrogen. Procedures are outlined for calculation of background and injected helium levels as well as displacement doses generated by neutrons and alpha particles. An example of the analysis method is shown for an experimental austenitic stainless steel containing boride particles and irradiated to 3 and 7 x 10/sup 22/ n/cm/sup 2/ (E > 0.1 MeV).

The filamentation instability has been identified as a possible pathology afflicting final transport even when gas pressure is high enough to eliminate the two-stream mode. This phenomenon is characterized by the spontaneous appearance of many narrow magnetic pinches within the pulse, with a corresponding increase in transverse temperature and emittance. If the time of flight of an ion exceeds one magnetic plasma period of the beam, then there is a danger of filamentation. However, large electrical conductivity (generated by the passage of the beam through the gas) inhibits mode growth for a pulse of finite duration. In addition, transverse thermal velocity damps perturbations of small transverse dimension, and therefore also acts to suppress mode growth. These ideas are developed here in a brief analytical treatment.

The motivation for detecting multiple quantum transitions by a Fourier transform experiment is reviewed and an experimental approach to high resolution multiple quantum spectra in dipolar systems along with results on some protonated liquid crystal systems are described. A simple operator formalism for the essential features of the time development is presented and some applications in progress are discussed. A spectrometer is described which is of pulsed Fourier transform design with superconducting magnet operating at a proton frequency of 195 MHz. Phase shifting was performed by a digitally controlled device under control of a pulse programmer. (FS)

Simulated transient tests were conducted on 234 cladding specimens from EBR-II irradiated mixed oxide fuel pins; approximately 75% of the specimens were from the fuel column region, with the remainder from the plenum and below the fuel column. The cladding specimens were taken from the N-E, N-F,, PNL-9, PNL-10, PNL-11, P-23A, P-23B, P-23C, and WSA-3 fuel pins irradiated at 15.2 to 37 KW/cm to burnup levels from 11 to 110 MWd/Kg. All the fuel pins used 20% cold worked Type 316 stainless steel cladding. Irradiation temperatures ranged from 370 to 725/sup 0/C with a peak fluence of 10/sup 23/ n/cm/sup 2/ (E > 0.1 MeV).

Most detailed fusion target design is done by numerical simulation using large computers. Although numerical simulation is briefly discussed, this lecture deals primarily with the way in which basic physical arguments, driver technology considerations and economical power production requirements are used to guide and augment the simulations. Physics topics discussed include target energetics, preheat, stability and symmetry. A specific design example is discussed.

Today there exists in the United States a large volume of nuclear wastes that result from both military and commercial activities. The United States has to date placed major emphasis on disposal in only one rock type--salt--whereas other nations have considered other rock types, such as granite in England and Sweden and clays in Belgium. No comprehensive evaluation of isolation in rocks other than salt has been made in the United States, and it is most appropriate that other rock types be evaluated both for constructing disposal sites in areas devoid of salt and also for having alternative waste management plans in case substantial problems are encountered in using salt as a disposal medium. To evaluate the state-of-the-art, research needs, and research priorities related to waste disposal in largely-impermeable rocks, scientists and engineers working on geologic aspects of nuclear waste disposal were brought together. The Geotechnical Assessment and Instrumentation Needs (GAIN) Symposium for Nuclear Waste Isolation in Crystalline and Argillaceous Rocks was held July 16-20, 1978 in Berkeley. This report and recommendations are the proceedings from that symposium. The location, design, and testing of a potential nuclear waste disposal site are both a geologic and an engineering problem. Disposal requires …

Heat and mass transfer due to convection in a two-dimensional model of the East Mesa geothermal system are presented. These results are an extension of those presented by Goyal and Kassoy (1977). (MHR)

The compatibility of candidate high-level waste (HLW) canister materials with deep geologic isolation environments is addressed. Results are presented which are applicable to the following repositories or test facilities: bedded and domed salt, sub-seabed sediment, and various types of hardrock. Such studies are an essential portion of the technological basis for terminal waste management. These studies will identify HLW canister or overpack materials satisfying appropriate requirements for barrier lifetime. Mechanical properties, as well as constraints on cost and consumption of critically limited materials, are also selection criteria. Lifetime objectives range from a minimum of several years for retrievability constraints up to several hundred years for retardation of near-field interactions (e.g., waste form leaching with potential radionuclide release to the geosphere) during the period of greatest HLW thermal output. A review of present and prior applicable corrosion results is presented. However, emphasis is on the results obtained from current laboratory and in situ HLW canister/corrosion programs at Sandia Laboratories. The effects of multiple variables on corrosion susceptibility and rates are briefly discussed and some applicable data given. It is possible to provide a canister/overpack barrier which can survive geologic isolation environments for periods of several hundred years.

The L/sub 2/ /sub 3/M/sub 2/ /sub 3/M/sub 2/ /sub 3// and L/sub 2/ /sub 3/M/sub 1/M/sub 2/ /sub 3/ Auger electron spectra from argon implanted by 1 keV ion bombardment in Be and Si crystals, were obtained using a double pass CMA operated in both the nonretard and retard modes. Background subtraction and loss-deconvolution were subsequently applied to obtain the final results. The argon-in-Be spectrum consists of a series of narrow peaks (FWHM less than 2 eV) which are sharper than those previously reported for the L/sub 2/ /sub 3/M/sub 2/ /sub 3/M/sub 2/ /sub 3/ spectrum from solid argon. Associating the major peak in the spectrum with the L/sub 3/M/sub 2/ /sub 3/M/sub 2/ /sub 3/(/sup 1/D/sub 2/) peak in the gas phase spectrum leads to an identification in terms of energy separations of the peak structure with the principal peaks of the gas-phase spectrum to within 0.5 eV. It's concluded that the transitions responsible for the Auger spectrum can be characterized as quasiatomic, although the multitude of gas-phase satellite peaks is not seen in the results. Peaks in the argon-in-Si spectrum are slightly broader than those in the argon-in-Be spectrum. As a result of screening by the …

Multiplicity distributions of particles created in p-p collisions with E/sub lab/ = 50 to 200 GeV are shown to contain at least one Poisson component which becomes dominant at multiplicities k greater than or equal to 1.5 (k). The mean values of both this component and of the (relatively low multiplicity residue) increase like E/sub lab//sup 1/2/; the relative weight of the Poisson component decreases approximately like E/sub lab//sup -0/ /sup 3/. If these trends continue beyond the available accelerator energies, one might expect the mean multiplicity to approach an E/sub lab//sup 1/2/ law beyond 10 TeV. 7 refs.

Infiltration studies have been carried out in a typical tract home in the San Francisco Bay area. Houses in this region as a result of the mild climate are loosely constructed, and show large air leakage rates. Infiltration rates of up to 1-1/4 air changes an hour were measured using a controlled flow tracer gas technique with nitrous oxide as the tracer gas. Air leakage rates were meausured using fan pressurization of the house with a range of pressures from 7.5 to 75 Pascals. In addition to weather data taken on site, pressure sensors mounted on the exterior walls were critical in establishing a pressure model for air infiltration. Measured inside--outside pressure differences were less than a tenth of those expected based upon wind speed measurements made on site. Measurements also show significant (20%) duct leakage and air flow between the attic, living space and crawl space.

The Clinch River Breeder Reactor Plant (CRBRP) sodium pumps are currently being designed and the prototype unit is being fabricated. In the design of these large-scale pumps for elevated temperature Liquid Metal Fast Breeder Reactor (LMFBR) service, one major design consideration is the response of the critical parts to severe thermal transients. A detailed internal fluid flow distribution analysis has been performed using a computer code HAFMAT, which solves a network of fluid flow paths. The results of the analytical approach are then compared to the test data obtained on a half-scale pump model which was tested in water. The details are presented of pump internal hydraulic analysis, and test and evaluation of the half-scale model test results.

The lattice location of implanted arsenic and antimony in single crystal silicon ((100) orientation) after pulsed laser annealing was studied using positive ion channeling-backscattering. The samples were implanted with 100 keV /sup 75/As or /sup 121/Sb to doses in the range 1 x 10/sup 15/ to 3 x 10/sup 16//cm/sup 2/ and subsequently annealed using the Q-switched output of a pulsed ruby laser (1.5 to 1.7 J/cm/sup 2/, approx. 50 x 10/sup -9/ sec pulse duration). Channeling measurements (2.5 MeV He/sup +/ ions) along major axial directions ((100), (110), and (111)) and detailed scans across the axes were used to determine the lattice location of the implanted dopants after annealing. In the dose range investigated, 98 to 99% of the As occupy substitutional sites. Antimony doses less than 1.5 x 10/sup 16//cm/sup 2/ yield similar results. Electrical measurements of the number of electrically active dopants support the high substitutional fractions observed by the ion channeling-backscattering measurements. Also reported are channeling results for /sup 75/As implanted (approx. 1 x 10/sup 16/ As/cm/sup 2/) samples that were annealed with an electron beam generator. Substitutional fractions (97 to 99%) comparable to laser annealing were obtained, but some nonuniformities across the samples were observed …

The major material requirements for inertial confinement fusion (ICF) reactors are presented. These requirements are defined and analyzed by first describing the environment created from the process of generating energy with ICF, and then analyzing the ICF reactor concepts which have been designed to cope with this hostile environment.