Evaluation of the application of heavy ion accelerators to ignite d-t pellets in a thermonuclear reactor is discussed. Accelerator design requirements considered include transport-limited current, beam injection conditions, and pulse bunching and focusing characteristics. The desirability of resonant and non-resonant accelerating structures is comparatively examined. The required power system switch tubes are discussed. It is concluded that heavy ion accelerators could offer a promising solution to the pellet-igniter problem. The advantages pointed out for this approach include electric efficiency greater than 10 percent, the possibility of high repetition rates (1 to 10 Hz), and a mature technological base. (RME)

The development of economic data for fusion power plants continued in a study estimating the potential impact of a shortage of materials important in fusion plant construction. In studies developing heat transfer and fluid flow design tools for fusion reactor blankets, preconceptual design studies were initiated to identify the potential design limits of water cooling in the first wall of Tokamak Next Step (TNS) concepts. In surface effects research clean gold samples were irradiated in the University of California (D,Be) neutron source for a neutron sputtering experiment. Light ion and neutron irradiation experiments have continued in studies of the effects of radiation on mechanical properties. The hardening response of 14 MeV neutron-irradiated nickel changed at high particle fluences (10/sup 16/ to 10/sup 17/ particles/cm/sup 2/) while the hardening response of 16 MeV proton-irradiated nickel did not, which may have been due to a difference in irradiation hardening mechanisms. The flux dependence of the damage microstructure and irradiation hardening of materials needs further study to clarify uncertainty about light ion and fusion neutron damage processes. Neutron irradiations of Ni, 316SS, and Nb wires and foils were completed. Work has continued in studies developing acoustic emission (AE) techniques for determining the prebreakdown …

A new concept for a power breeder reactor that consists of an accelerator-driven subcritical thermal fission system is proposed. In this system an accelerator provides a high-energy proton beam which interacts with a heavy-element target to produce, via spallation reactions, an intense source of neutrons. This source then drives a natural-uranium-fueled, light-water-moderated and -cooled subcritical blanket which both breeds new fuel and generates heat that can be converted to electrical power. The report given presents a general layout of the resulting Accelerator Driven Light Water Reactor (ADLWR), evaluates its performance, discusses its fuel cycle characteristics, and identifies the potential contributions to the nuclear energy economy this type of power reactor might make. A light-water thermal fission system is found to provide an attractive feature when designed to be source-driven. The equilibrium fissile fuel content that gives the highest energy multiplication is approximately equal to the content of /sup 235/U in natural uranium. Consequently, natural-uranium-fueled ADLWRs that are designed to have the highest energy generation per source neutron are also fuel-self-sufficient; that is, their fissile fuel content remains constant with burnup. This feature allows the development of a nuclear energy system that is based on the most highly developed fission technology …

Bulk mixing coefficients were measured for single plane water flow in a simulated rod bundle with a pitch to diameter ratio of 1.10. A tracer technique employing Rhodamine B as the tracer and measuring fluorescence was used. Isokinetic sampling was achieved by using a pressure balance method. The results were corrected for both entrance effects and diversion crossflows. The results showed a change in Reynolds number behavior as the laminar sublayer began to ''choke'' the turbulent mixing. This, and a review of other mixing experiments, suggested that secondary flows do not compensate for laminarization and that turbulent mixing decreases as the pitch to diameter ratio decreases for values of P/D less than 1.05 in a manner similar to that predicted by Ramm et al. Concentration profiles were measured through the clearance gap and the values of the gradient were used to calculate the gap averaged circumferential eddy diffusivity for mass. A discussion of the eddy diffusivity concept and its applicability to turbulent mixing is presented.

With the combination of low hydrogen to coal ratio, high coal feed rate and larger total quantity of coal fed, considerable liquid product is being condensed and collected. Experimental runs conducted at 750/sup 0/C and 800/sup 0/C at pressures up to 3000 psi of hydrogen show overall hydrocarbon yields and particularly gaseous hydrocarbon yields to increase with pressure to approximately 60 percent at 3000 psi. At 750/sup 0/C approximately one third (20 percent) of this yield is in the form of liquid products (half BTX and half greater than or equal to C/sub 9/) while at 800/sup 0/C the yield is almost all methane with less than 3 percent of liquids produced. Preliminary results of the effect of residence time on product yield and distribution shows that at 3000 psi of hydrogen and 800/sup 0/C, gaseous product yield increase and liquid yields decrease as the residence time is increased from 2.3 to 9.2 seconds. Under almost identical conditions at 750/sup 0/C, all product yields increased with approximately the same increase in residence time. Economic studies of the Flash Hydropyrolysis Process (FHP) are continuing. A detailed analysis of a 25,000 ton/day coal conversion plant utilizing FHP shows the discounted cash flow …

In January 1976, the Water Resources Division of the U.S. Geological Survey asked Lawrence Livermore Laboratory to conduct a feasibility study for automation of the National Water Quality (NWQ) Laboratory in Denver, Colorado (formerly Denver Central Laboratory). Results of the study were published in the Feasibility Study for Automation of the Central Laboratories, Lawrence Livermore Laboratory, Rept. UCRL-52001 (1976). Because the present system for processing water samples was found inadequate to meet the demands of a steadily increasing workload, new automation was recommended. In this document we present details necessary for future implementation of the new system, as well as descriptions of current laboratory automatic data processing and analytical facilities to better define the scope of the project and illustrate what the new system will accomplish. All pertinent inputs, outputs, and other operations that define the project are shown in functional designs.

The objective of this project was to develop a form-stable, crystalline polymer pellet TES bed material, useful in the 120 to 140/sup 0/C temperature range suitable for solar absorption air conditioning applications. This objective was achieved with a Si-O-Si crosslinked HDPE pellet material, demonstrated to have a high heat of fusion value (46 cal/g, approximately 98% of the HDPE's heat of fusion value prior to crosslinking). Further, on melt/freeze cycling of these TES pellets through 400 cycles in ethylene glycol, they retained nearly 100% of their initial heat of fusion value, and had excellent form-stability characteristics, with little or no inter-particle adhesion. Appropriate testing of this TES pellet material, from analytical (DSC) to a one gallon lab-scale TES unit, and finally to a 60 gallon prototype TES demonstration unit, consistently verified these results. C-C crosslinked PE products, which were slightly inferior to the Si-O-Si crosslinked PE in terms of good heat of fusion and form-stability properties, were also developed and are potential alternatives to the prime PE TES product.

Measurements of the noise power spectra of tin and lead films at the superconducting transition in the frequency range of 0.1 Hz to 5k Hz are reported. Two types of samples were made. Type A were evaporated directly onto glass substrate, while Type B were evaporated onto glass or sapphire substrate with a 50A aluminum underlay. The results were consistent with a thermal diffusion model which attributes the noise to the intrinsic temperature fluctuation in the metal film driven with a random energy flux source. In both types of metal films, the noise power was found to be proportional to (V-bar)/sup 2/ ..beta../sup 2//..cap omega.., where V-bar was the mean voltage across the sample, ..beta.. was the temperature coefficient of resistance and ..cap omega.. was the volume of the sample. Correlation of noises in two regions of the metal film a distance d apart was detected at frequencies less than or = D/..pi..d/sup 2/. A possible explanation of the noises using quantitative boundary conditions and implications of this work for device applications are discussed. Theoretical and experimental investigation are reported on the resistance of superconductor-normal metal-superconductor sandwiches near T/sub c/. The increase in SNS resistance is attributed to the penetration …

The FORTRAN codes COREL, RASE4 and DAMG2 can be used to calculate quantities associated with ion implantation range and energy deposition distributions within an amorphous target, or for ions incident far from low index directions and planes in crystalline targets. RASE4 calculates the projected range, R/sub p/, the root mean square spread in the projected range, ..delta..R/sub p/, and the root mean square spread of the distribution perpendicular to the projected range ..delta..R/sub perpendicular to/. These parameters are calculated as a function of incident ion energy, E, and the instantaneous energy of the ion, E'. They are sufficient to determine the three dimensional spatial distribution of the ions in the target in the Gaussian approximation when the depth distribution is independent of the lateral distribution. RASE4 can perform these calculations for targets having up to four different component atomic species. The code COREL is a short, economical version of RASE4 which calculates the range and straggling variables for E' = 0. Its primary use in the present package is to provide the average range and straggling variables for recoiling target atoms which are created by the incident ion. This information is used by RASE4 in calculating the redistribution of deposited …

The design of the prototype neutral beam injection system for TFTR is nearing completion at the Lawrence Livermore Laboratory. This paper describes some of the features of the facility at the Lawrence Berkeley Laboratory where this prototype will be assembled and tested.

The final results are summarized of a Plant Systems/Components Modularization Study based on Stone and Webster's Pressurized Water Reactor Reference Design. The program has been modified to include evaluation of the most promising areas for modular consideration based on the level of the Sundesert Project engineering design completion and the feasibility of their incorporation into the plant construction effort.

Fluid bed densities and levels are usually obtained from measurement of differential pressures between taps with a known vertical separation. Historically, this measurement has been difficult in high pressure coal gasification processes primarily due to plugging of the pressure taps and process instrument tubing. Likewise, the achievement of accurate and reliable pressure and differential pressure recordings is affected by similar circumstances. These typical problems were experienced at the SYNTHANE Pilot Plant at Bruceton which is operated for the U.S. Energy Research and Development Administration by the C.E. Lummus Company. Major changes were required in instrument location and selection, piping configuration, and methods of purging. Consistent and accurate data is now obtained. Recommendations for the installation and operation of such instruments are given.

A comprehensive survey of the current state of the absorption cooling technology has been conducted. This survey discusses the basic and applied absorption cooling/heating technology, analyses the current state of the art including the discussion of limitations and possible solutions, identifies areas where promising developments are indicated, lists the current products and activities of the absorption industry, and presents the current RD and D efforts of the U.S. government. The main subjects covered in the survey are as follows: Principles of absorption cooling technology (NH/sub 3/-H/sub 2/O cycle and H/sub 2/O-LiBr Cycle), Adaptation of absorption cooling technology for solar cooling applications, Thermal performance of absorption cooling units, Comparison of NH/sub 3/-H/sub 2/O absorption with H/sub 2/O-LiBr absorption, Commercially available solar absorption units, General trends of the absorption cooling industry toward solar application, Absorption cooling system performance in actual installations, Limitations of absorption cooling technology, Solar-powered absorption heat pumps, and U.S. ERDA activities relating to solar absorption cooling. The treatment of the subjects is intended to be basic and comprehensive in order that the general readers may understand the current aspects of absorption technology in solar cooling applications. 36 references.

Data and an analysis are presented showing that when the operating pellet-cladding gap size of contemporary UO/sub 2/ fuel rods is carefully considered, the gap conductances are closely proportional to the thermal conductivities of the fill gases. Pellet-cladding gap eccentricity is shown to raise the gap conductance appreciably in cases of high thermal gradients across the gap. Ignoring the azimuthal heat flow can lead to an underestimation of the thermal time constant of the rod, resulting in a slower calculated thermal response during power transients. The data for this report were obtained during the startup of the NRC-RSR/BPNL test assembly IFA-431 in the Halden Boiling Water Reactor in Norway.

Two asymptotic worlds, one based on solar energy, the other based on nuclear energy, are compared. The total energy demand in each case is 2,000 quads. Although the Sun can in principal supply this energy, it probably will be very expensive. If the energy were supplied entirely by breeders, the nuclear energy system would pose formidable systems problems--particularly safety and proliferation. It is suggested that in view of these possible difficulties, all options must be kept open.

Tests were performed on a ''typical'' residential hot water boiler to evaluate the energy saving potential of reduced boiler water temperature. A significant reduction of annual fuel consumption was determined based on detailed efficiency measurements combined with the BNL Seasonal Performance Evaluation Computational Program. The energy saving has been attributed to reduced off-cycle heat losses resulting from the lower boiler operating temperature.

An analysis of factors which influence the optical transparency of hot-pressed CdCr/sub 2/S/sub 4/ at 10.6 ..mu..m was made. It was found that multiphonon absorption, an intrinsic process, is the factor which limits the ultimate achievable absorption coefficient, ..cap alpha.., at 10.6 ..mu..m. Several extrinsic processes have also been found to affect the transmission of hot-pressed CdCr/sub 2/S/sub 4/. In sufficient concentration, oxygen appearing as SO/sub 4//sup 2 -/ or similar sulfate complexes contribute to ..cap alpha.. through an absorption band centered at 9.3 ..mu..m. Cr/sub 2/O/sub 3/, appearing as a second phase with a different index of refraction, causes scattering in concentrations as low as .01 mole percent. Despite the identification of these processes, possible uncertainties in the value of reflectivity, and surface losses, prevent the establishment of a definite lower limit on the absorption coefficient. It was firmly established that ..cap alpha.. at 10.6 ..mu..m is decreased significantly upon cooling to 77/sup 0/K. Thus, an ..cap alpha.. of .5 cm/sup -1/, which would give a transmission of 85 percent in an optical isolator, still appears to be possible. CdCr/sub 2/Se/sub 4/ is suggested as an alternative material since the potential of a lower intrinsic ..cap alpha.. is a …

Separate abstracts were prepared for 20 sections of the report. (HLW)

The objective of this report is to present the mathematical basis of the COBRA-IV computer program (Wheeler et al., 1976) being developed by Battelle, Pacific Northwest Laboratory. The COBRA-IV code is an extended version of the COBRA-IIIC subchannel analysis code that computes the flow and enthalpy distributions in nuclear fuel rod bundles and cores for both steady state and transient conditions (Rowe, 1973).

The various isotope-dependent and independent atomic and molecular properties that pertain to the isotopic difference between the zero point energy (ZPE) shifts upon condensation were derived. The theoretical development of the change of the ZPE associated with the internal molecular vibrations, due to the condensation of the gaseous molecules, is presented on the basis of Wolfsberg's second-order perturbation treatment of the isotope-dependent London dispersion forces between liquid molecules. The isotope effect on the ZPE shift is related to the difference between the sums of the integrated intensities of the infrared absorption bands of the two gaseous isotopic molecules. The effective atomic charges are also calculated from available experimental infrared intensity data. The effects of isotopic substitutions of carbon-13 for carbon-12 and/or deuterium for protium, in ethylene, methane, and the fluorinated methanes, CH/sub 3/F, CH/sub 2/F/sub 2/, CHF/sub 3/, and CF/sub 4/, on the ZPE shift upon condensation are calculated. These results compare well with the Bigeleisen B-factors, which are experimentally obtained from vapor pressure measurements of the isotopic species. Each of the following molecular properties will tend to increase the isotopic difference between the ZPE shifts upon condensation: (1) large number of highly polar bonds, (2) high molecular weight, (3) …

A critical review of the thermal non-equilibrium phase change models applicable to the water reactor safety calculations is presented. Four specific areas are discussed: (1) rapid depressurization (flashing), (2) post-dryout heat transfer, (3) direct contact condensation, and (4) sub-cooled boiling. The models have been judged from a mechanistic viewpoint, and the areas where further work is needed have been pointed out. It is suggested that when a phase change occurs due to a difference in the bulk fluid temperatures, the non-equilibrium phase change process can be viewed as a linear, non-homogeneous thermal relaxation phenomenon. Direct measurements of the actual phase change rates and the interfacial area densities are emphasized. Finally, a recommendation for the volumetric vapor generation rates applicable to the above four specific areas is given.

A cost/benefit study was made to determine the cost and effectiveness of radioactive waste (radwaste) treatment systems for decreasing the release of radioactive materials and chemicals from a model uranium hexafluoride (UF/sub 6/) production plant using the fluorination-fractionation (dry hydrofluor) process, and to evaluate the radiological impact (dose commitment) of the released materials on the environment. This study is designed to assist in defining the term as low as is reasonably achievable (ALARA) in relation to limiting the release of radioactive materials from nuclear facilities. The model plant processes 10,000 metric tons of uranium per year. Base-case waste treatment is the minimum necessary to operate the process. Effluents meet the radiological requirements listed in the Code of Federal Regulations, Title 10, Part 20 (10 CFR 20), Appendix B, Table II, but may not be acceptable chemically at all sites. Additional radwaste treatment techniques are applied to the base-case plant in a series of case studies to decrease the amounts of radioactive materials released and to reduce the radiological dose commitment to the population in the surrounding area. The costs for the added waste treatment operations and the corresponding dose commitment are calculated for each case. In the final analysis, radiological …

An Integrated Community Energy System Program in Independence, Missouri is described and results of Phase I are summarized. Five tasks of Phase I are: preliminary energy analysis and institutional assessment, conceptual design of ICES, firming-up of commitments, and work management plan. The program involves developing a small coal-fired unit that can be effectively integrated into the total community environment. (MCW)

One of the seven producing gas wells in the Rulison Field, Garfield County, Colorado, was selected for a massive hydraulic fracturing experiment. The fracture treatment (Aug. 1976) was applied in two stages treating separately the gross perforated intervals from 6198 to 6363 ft (Stage 1) and 5170 to 5630 ft (Stage 2). 485,000 gallons of gelled water, 1,070,000 pounds of sand, and 500 scf of nitrogen per barrel were used. A brief cleanup flow period was allowed between stages. The treatment was designed to extend a fracture approximately 1400 ft from the wellbore with a propped fracture width of 0.176 inches. The production increase was expected to range from 5.5 to 6.2 times the pre-treatment rate of 35,000 scf per day. Results of the massive hydraulic fracturing treatment were poor. Production of gas was enhanced by a factor of less than 2. The average flow rate during early 1977 was about 50,000 cubic feet per day. The lack of success is attributed to both low reservoir permeability and a restricted reservoir due to sand lenticularity.