A P/sub 3/, 218 neutron group cross-section library in the AMPX master interface format has been generated from ENDF/B-IV data for 65 nuclides of primary interest in criticality safety calculations. The library was generated with the AMPX modular code system. Procedures used to generate the cross sections and the organization of the library are described.

Direct energy converters for use on controlled fusion reactors utilize electrodes operated at elevated voltages and temperatures. The insulating elements that position these electrodes must support large voltages and under some circumstances large thermal gradients. It is shown that even modest thermal gradients can cause major alterations of the electric-field distribution within the insulating element.

The effects of airblast due to explosive detonation in close proximity of a concrete wall are investigated analytically. Estimates are obtained both for the spalling of the back-face of the concrete wall and for the overall wall response produced by the total impulsive load of the air blast. Assuming elastic wave propagation in the concrete wall, it is found that as spall thickness increases the spall velocity decreases. This holds for normal as well as oblique wave incidence on the back-face of the wall. Therefore, for debris which has significant mass, the ejection velocity produced by spalling action alone is quite moderate. Plastic yield-line analysis of the wall segment subjected to the impulsive loading of the air blast indicates that for sufficiently large explosions substantial displacements and peak velocities can occur in typical shield walls. Thus for close-in explosions severe wall damage and/or breaching should be expected. Also coupling between spallation and the gross wall motion is possible. This occurs when debris produced by spalling action is ejected at high velocities by the rapid wall motion.

Aerojet Nuclear Company performed an experiment at the Westinghouse Canada Ltd. water loop to try to verify the performance of a Transit Time Flowmeter to ultimately measure two-phase flow rates. The recorded data from that experiment were made available and analyzed at Argonne National Laboratory using a transfer function cross-correlation technique. The theoretical background for the transfer function method of analysis and the results of the data analysis are presented. Strong correlation peaks, which are very close to the expected delay times, were found in certain portions of the data.

The equation of the normalized COD design curve recently proposed in the UK as a basis for determining allowable crack sizes is derived from the Equivalent Energy approximation for the J Integral. It is also shown that another approximation for the J Integral recently proposed by Westinghouse is mathematically equivalent to the normalized COD approach.

The bibliography presented contains 100-word abstracts of reports to the U.S. Nuclear Regulatory Commission concerning operational events that occurred at boiling-water reactor nuclear power plants in 1975. The report includes 1169 abstracts, arranged alphabetically by reactor name and then chronologically for each reactor, that describe incidents, failures, and design or construction deficiencies that were experienced at the facilities. Key-word and permuted-title indexes are provided to facilitate location of the subjects of interest, and tables that summarize the information contained in the bibliography are provided. The information listed in the tables includes instrument failures, equipment failures, system failures, causes of failures, deficiencies noted, and the time of occurrence (i.e., during refueling, operation, testing, or construction). Seven of the unique events that occurred during the year are reviewed in detail.

The bibliography presented contains 100-word abstracts of reports to the U.S. Nuclear Regulatory Commission concerning operational events that occurred at pressurized-water reactor nuclear power plants in 1975. The report includes 1097 abstracts, arranged alphabetically by reactor name and then chronologically for each reactor, that describe incidents, failures, and design or construction deficiencies experienced at the facilities. Key-word and permuted-title indexes are provided to facilitate location of the subjects of interest, and tables summarizing the information contained in the bibliography are presented. The information listed in the tables includes instrument failures, equipment failures, system failures, causes of failures, deficiencies noted, and the time of occurrence (i.e., during refueling, operation, testing, or construction). A few of the unique events that occurred during the year are reviewed in detail.

Tabulated data are presented on: the monthly deposition of /sup 89/Sr and /sup 90/Sr at some 100 world land sites; the content of lead and /sup 7/Be, /sup 95/Zr, /sup 137/Cs, and /sup 144/Ce in samples of surface air from various world sites; and the content of /sup 90/Sr in samples of milk, drinking water, and animal and human diets collected at various locations throughout the USA. (CH)

A critical review was made of reported information from laboratory studies of plant uptake of transplutonic elements plus neptunium. The available data are meager but indicate that the uptake of Np is the greatest followed by Am and Cm. The data are not sufficient to provide recommended values for use in hazard calculations but they do indicate that the actinides other than plutonium will be accumulated in plants to a greater degree than plutonium.

This report describes a successful test performed to determine the capabilities of a unique metal- cutting tool called the arc saw. The test was sponsored by the Contaminated Equipment Volume Reduction (CEVR) program being conducted for the Energy Research and Development Administraction by the Atlantic Richfield Hanford Company.

Quarterly report of the Areawide Waste Treatment Management Plan in/near San Antonio, Texas describing the program's activities, contract status, finances, relationships with other agencies, and additional information for the second quarter of 1976.

This report has the goal of presenting for the CTR designer and material supplier potentially significant problem areas in materials manufacturing and in structural material resources projected for potential application in fusion power reactor construction. The projected material requirements are based on presently available bills-of-materials for conceptual CTR designs used for constructing a hypothetical fusion power generating capacity of 10/sup 6/ MW(e) maturing exponentially over a 20-year period. The projected elemental requirements, the ratio of these requirements to the projected total U.S. demand, and the salient problems currently identified with the CTR use of these elements are summarized. The projected requirements are based upon a ''model'' industry, which is described, and the estimated potential use of molybdenum, niobium, vanadium, and tantalum as blanket structural materials.

This document describes a high power, high voltage power supply system required to operate sustaining neutral beam (NB) sources as would be used in the Baseball II-T Multiple Beam Project. Two such systems would be needed. Appended are site plan installation drawings.

Progress is reported for a research program to demonstrate an experimental gas turbine powered automobile which would meet the 1978 Federal Emissions Standards, have significantly improved fuel economy and be competitive in performance, reliability and potential manufacturing cost with the conventional piston engine powered, standard size American automobile. Chrysler Corporation's Sixth Generation Gas Turbine Engine, having been selected as most representative of the state-of-the-art at the beginning of this program, has been used as the Baseline Engine. This is a 4:1 pressure ratio regenerative engine with variable power turbine nozzles which meets the .41 HC, 3.4 CO, 3.0 NOx grams/mile original 1975 emissions standards. Baseline vehicles are intermediate-size, 4-door sedans modified to accept the turbine engines. The Baseline cars are being actively utilized in a variety of Bicentennial/Energy related displays and demonstrations. All Baseline Engine improvement tasks have been completed. Emissions tests using COED coal derived fuel were conducted. The first Upgraded Engine was assembled, installed in a test cell, and initial test runs up to 70% speed were conducted. Control of the gas generator shaft instabilities which have resulted in failures of the gas lubricated bearing, was demonstrated by providing a low spring rate, squeeze film damping, and reducing …

A Bayesian Zero-Failure (BAZE) reliability demonstration testing procedure is developed. The procedure may be used to verify component failure rates associated with both real-time dependent and cycle-dependent chance failure mechanisms. A constant falure-rate model with a gamma prior distribution is assumed. The procedure is used to obtain sample test plans for components of a proposed Rankine power conversion system.

A simple yet highly accurate method for approximately calculating spectrum-averaged beta energies and beta spectra for radioactive nuclei is presented. This method should prove useful for users who wish to obtain accurate answers without complicated calculations of Fermi functions, complex gamma functions, and time-consuming numerical integrations as required by the more exact theoretical expressions. Therefore, this method should be a good time-saving alternative for investigators who need to make calculations involving large numbers of nuclei (e.g., fission products) as well as for occasional users interested in restricted number of nuclides. The average beta-energy values calculated by this method differ from those calculated by ''exact'' methods by no more than 1 percent for nuclides with atomic numbers in the 20 to 100 range and which emit betas of energies up to approximately 8 MeV. These include all fission products and the actinides. The beta-energy spectra calculated by the present method are also of the same quality.

The citations are arranged under: actinides, alpha particles, americium, beta particles, calcination, cements, ceramics, cesium, containers, decontamination, evaporation, fluidized bed, glass, ground release, high-level wastes, incinerators, liquid wastes, marine disposal, melting, nonradioactive waste disposal, Pu, radiation doses, radiation protection, disposal, processing, radionuclide migration, Ru, safety, separation processes, soils, solidification, solid wastes, stack disposal, temperature, thermal conductivity, transmutation, tritium, underground disposal, U, volatility, and waste disposal/management/processing/storage/transportation. (DLC)

This report is on Bibliography on Multinational Banking and Related Aspects of Private International Finance 1960-MID 1976.

This bibliography on the biology of the transuranium elements is a revision of one issued in 1973 (BNWL-1782). It includes essentially all of the citations from the earlier document, a few corrections and additions from the older literature, plus the new literature to mid-1975. It also includes a subject-matter index not present in the original document.

This report addresses a biphase turbine bottoming cycle for a diesel engine.

Impact on pin diameter optimization and breeding performance from either a constant coolant velocity (25 ft/sec) constraint or a constant fuel bundle pressure drop (40 psi) constraint has been evaluated, and comparisons of these results are given. The 40 psi fuel bundle pressure drop was chosen not to imply a limit of pump technology, but because it corresponds to acceptable coolant velocities in the range of 25 ft/sec ro 35 ft/sec for various pin diameters and linear heat ratings.

In the management of the adverse byproducts of nuclear energy, the general problem is centered in the post-reactor discharge phases. Various waste streams are generated in the reprocessing and fuel manufacturing plants which add both volume and physicochemical diversity to the nuclear fuel waste management problem. Of these streams, the high level waste (HLW) and the clad waste streams carry the principal radiological hazard and thermal power burdens when considering post reactor-discharge times in excess of roughly a year and reasonable contamination factors. In order to measure the relative importance of the high level and clad waste streams within the context of a reasonable nuclear power scenario, various technical and hazard indices are compared for the light water, enriched uranium fueled, reactor (LWR(U)). For the clad waste, two fuel models are used for the volume comparison: the Reference Fuel Assembly (RFA) and the Diablo Canyon reference fuel model (DC). The more extensive data available for the Diablo Canyon model on radioactivity and thermal power are used in the comparison of these indices. Most of this review pertains to a burnup of 33GWD/MT. A brief analysis is given of the effect of burnup and fuel model on certain clad waste characteristics. …

Preliminary EMP calibration data on magnetic thin film current sensors has been obtained. The Air Force Weapon Lab's Coaxial Chamber was used as the EMP standard and a current pulse width of 40 ns was used. It was found that the sensitivity of the sensors can be increased by controlling the width of the 90/sup 0/ wall strip and that the current scales for the sensors were linear. The results strongly suggest that the dimensions of the sensors can be varied to meet different measurement requirements.

A computer code, titled GEOCOST, has been developed at Battelle, Pacific Northwest Laboratories, to rapidly and systematically calculate the potential costs of geothermal power. A description of the cost models in GEOCOST for the geothermal power plants is given here. Plant cost models include the flashed steam and binary systems. The data sources are described, along with the cost data correlations, resulting equations, and uncertainties. Comparison among GEOCOST plant cost estimates and recent A-E estimates are presented. The models are intended to predict plant costs for second and third generation units, rather than the more expensive first-of-a-kind units.