Since the enactment of the Water Quality Act of 1965, there has been an increasing concern over the quality of the nation's waters. Adoption of temperature standards of water bodies, combined with the economics of scale, is resulting in increased use of alternatives to once-through cooling systems, particularly ponds and towers. Approximately 60 steam-electric power plants with capacities greater than 60 electrical megawatts use cooling ponds. This report documents a review of cooling pond technology in which major emphasis was placed on examination of engineering and environmental aspects of design, mathematical and physical modeling, use of sprays, and economics.

Swelling in prototypic FTR cladding and duct specimens is being determined from a series of three irradiations designed to cover a range of temperatures approximately 800 to 1500/sup 0/F and peak fluences of approximately 1 x 10/sup 22/, 6 x 10/sup 22/, and 1 x 10/sup 23/ n/cm/sup 2/. The length change measurements for the low fluence irradiation have been completed and are summarized in this report. No swelling, only shrinkage, was found in the 20 percent cold worked Type 316 stainless steel cladding specimens. This shrinkage is of the same magnitude and has the same temperature dependency as unirradiated, control samples. Annealed specimens did swell slightly. Details of the experiment and analysis are given.

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The authors describe several types of small liquid xenon-filled chambers, each optimized for a particular property such as a real-time spatial resolution of {+-} 15 {mu}, a time resolution of {+-} 10{sup -7} sec, or a pulse height of 10{sup -12} coulomb. Larger chambers combining all these properties will be of great value at NAL energies, and they describe some of the techniques necessary for their construction.

The increasing availability of short lived gamma and positron emitting isotopes, coupled with the importance of dynamical studies and better imaging, has generated the need for an improved {gamma}-ray camera. The authors discuss a new type of {gamma}-ray camera which makes use of electron avalanches in liquid xenon. A configuration currently under development is shown in Figure 1. The successful operation of a liquid xenon proportional counter was recently reported. The liquid xenon camera promises better spatial resolution and higher counting rate than the existing NaI(Tl) scintillation camera. The spatial resolution for {gamma} rays is in principle limited only by the range of photoelectrons in liquid xenon, which is < 0.2 mm for energies < 1 MeV. A counting rate of 10{sup 6} C/s or more appears possible. As a result of the better resolution and high counting rate capability, the definition of the picture is improved. In addition, the high counting rate capability makes possible dynamic studies which were previously unfeasible. Although they expect the energy resolution with liquid xenon to be superior to that of NaI, the preliminary measurements show 17% FWHM for 279 keV {gamma}'s. Improvements are expected by using better geometry and smoother wire.

Recent years have witnessed the development of accelerators of ever-larger current, both peak and average, as well as a proliferation of storage rings of ever-greater luminosity. Consequently, there is considerable interest in and growing concern with, the phenomena which limit beam currents and beam densities, namely, the collective modes of behavior of relativistic particle beams. Furthermore, it has been demonstrated that the collective behavior can be controlled, at least to some extent, turned to good advantage, and employed for collective acceleration in devices such as the electron ring accelerator. Quite naturally then, almost every accelerator conference during the last five years has had a review paper on collective effects, while at the same time the number of original papers in this area now exceeds many hundreds. And thus I am faced with the dilemma of being unable to give a comprehensive and complete review (such a review, incidentally, would be most valuable; in my judgment the time is ripe for a comprehensive monograph on the subject.), and yet finding it difficult, in a brief review, to be comprehensible, balanced, and yet fresh. I have resolved the dilemma by firstly supplying sufficient references as to allow the interested reader to readily …

A prototype liquid xenon {gamma}-camera has been constructed and preliminary results obtained. The sensitive volume is 7 c x 7 cm in area and 1.5 cm thick. Orthogonal coordinates for each interacting {gamma}-ray are provided by 24 anode wires 5 {micro} in diameter spaced 2.8 mm apart and 24 cathode strips.

On the basis of our present understanding of the physical phenomena involved in an electron ring accelerator (ERA), a theoretical study is made of the performance which might be expected for an ERA. Rigorous upper bounds are obtained on the rate of energy gain, from which it is shown that, in order to prevent azimuthal instability, parameters must be selected such that (for reasonable fields, injector properties, etc., but with no safety factors) the proton energy gain is less than 80 MeV/m. Numerical examples and approximate formulas are given for the properties of rings satisfying the stability conditions for both azimuthal oscillations and ion-electron oscillations. It is found that for reasonable fields and injector properties, but without safety factors, the useable proton energy gain is less than 45 MeV/m.

This report contains an explanation of the various sources and uses of federal government unified budget funds, specifically how they have been employed under different presidential administrations.

A predictive model of the time-dependent evolution of radial Pu/U + Pu gradients in operating nonmolten mixed oxide fuels is being developed. This model is based on preferential evaporation-condensation and vapor transport of metal-bearing species either along cracks and porosity channels within the fuel or inside closed pores migrating up the temperature gradient; equilibrium thermodynamics are applied to calculate the continually changing vapor composition over the hot fuel. Predictions of the model are used in combination with recent in-pile experimental data (from nonmolten mixed oxide fuel pins irradiated in EBR-II from 0.2 to about 11 at. % burnup at varying powers) to delineate the key parameters in radial actinide redistribution. A correlation between fuel stoichiometry (O-to-Pu ratio) and the degree of redistribution (described by an enrichment factor ..gamma../sub Pu/) identified, however, the degree of restructuring of the fuel - as determined by the peak linear power rating, time at this power, and the initial fuel density - also has a strong influence on the final value of ..gamma../sub Pu/. Certain kinetic features of the process and intended modifications to the present model are discussed, and evidence for axial actinide vapor transport in an irradiated annular fuel is also presented.

The expansion characteristics of the detonation products of a high-explosive energy source used to simulate the pressure-volume change relationships for sodium-vapor expansions during hypothetical core disruptive accidents in a Fast Test Reactor were determined experimentally. Rigid cylinder-piston experiments performed at two scales (ratio 1:3) were undertaken to determine a pressure-volume relationship as a function of source mass and expansion environment. Some of these measurements were compared with code calculations for the source.

The biomedical program of the Laboratory of Nuclear Medicine and Radiation Biology for Fiscal Year 1974 is conducted within the scope of the following categories: Effects of Radiation of Living Organisms; Molecular and Cellular Radiobiology; Land and Fresh Water Environmental Sciences; Radiological and Health Physics and Instrumentation; and Nuclear Medical Research. (ACR)

Conceptual designs for 6- and 18-subassembly casks are presented. The casks are intended for transport of LMFBR spent fuel which has decayed a minimum of 30 days. These casks use sodium as the primary coolant, an auxiliary shield coolant system in normal operation, heavy steel members as both gamma shield and structure, and a eutectic mixture of LiOH and NaOH as a neutron shield. The analysis indicates that there will be no leakage of coolant or fission products under normal or hypothetical accident conditions.

This report describes a simple, efficient, and flexible program for cubic spline interpolation in one dimension, suitable for inclusion in the ANL Subroutine Library and in an interactive timesharing system. Most of the cubic spline programs already available either restrict the boundary conditions to knowledge of the first derivative at both end points, or require the second derivatives to vanish at these points. The program described here removes these restrictions and enables the user to adopt boundary conditions appropriate for his own problem. The advantage is demonstrated for the extreme case of interpolating the function x log (1/x), which has singularities in all its derivatives at x = 0.

The Met-L-X storage unit and fixed-pipe system performed adequately, but the distribution provided by the nozzles as located is not satisfactory. Relocation of the nozzles does not appear to offer much promise for improvement because the number of nozzles required would necessitate a piping array nearly impossible to design or install around existing equipment. It would leave little room for equipment to be protected in a new installation. The tests reported did not address the question of whether Met-L-X powder will extinguish a sodium fire even if properly applied.

The windstorm of January 11 caused a minor amount of damage to the Hanford Reservation and Hanford vicinity. Damage sustained to Hanford Reservation structures (roofing, flashing, fences, windows) was approximately $20,000. One building did receive structural damage to roof members. Evidence that wind pressures did not reach 30 lb/ft{sup 2} during the January 11 windstorm was provided in the fact that specially designed exterior wall panels did not fail. These panels were designed and carefully proof-tested to insure that they would fail at a loading of 30 lb/ft{sup 2} as a requirement of structural safety in the original design-construction program in 1952-1954. There was one power outage on the Hanford Reservation due to the January 11 windstorm (Rattlesnake Mountain Observatory). Damage to power lines and electrical facilities amounted to about $1600. Damage to structures in the Hanford vicinity (excluding the Hanford Reservation) from the January 11 windstorm was estimated to cost $13,000. This does not include damage to private residences, etc., which has been estimated by others to be near $250,000. Power line damage in the Hanford vicinity amounted to about $80,000, of which $60,000 was accounted for in the loss of four transmission towers in the tie-line between Priest …

Estimates are made of United States resources of coal, petroleum liquids, natural gas, uranium, geothermal energy, and oil from oil shale. Accuracy of the estimates probably ranges from 20 to 50 percent for identified-recoverable resources to about an order of magnitude for undiscovered-submarginal resources. The total cost resource base in the United States is estimated to be about 3,200 billion tons, of which 200 to 390 billion tons can be considered in the category identified and recoverable. It is estimated that the total resource base for petroleum liquids is about 2,900 billion barrels, of which 52 billion barrels is identified and recoverable. Of the total resource base, some 600 billion barrels is in Alaska or offshore from Alaska, 1,500 billion barrels is offshore from the United States, and 1,300 billion barrels is onshore in the conterminous United States. Identified-recoverable resources of petroleum liquids corresponding to these geographic units are 11, 6, and 36 billion barrels, respectively. The total natural gas resource of the United States is estimated to be about 6,600 trillion cubic feet, of which 290 trillion cubic feet is identified and recoverable. Uranium resources in conventional deposits, where uranium is the major product, are estimated at 1,600,000 tons …

The HELP documents provide SPEAKEASY users with concise definitions of most of the words available in the current processors. In this report, the documents are given in a variety of formats to enable one to find specific information quickly. The bulk of this report consists of computer read-out of the HELP library via SPEAKEASY.

This book is an outgrowth of activities of the Benchmark Problem Committee of the Mathematics and Computation Division of the American Nuclear Society.

A variety of position-sensitive single-wire proportional counters with lengths up to 90 cm have been built and tested in the focal plane of the Enge split-pole spectrographs at the Argonne tandem accelerator and cyclotron. This report, which describes the counters, the associated electronics, and the data-handling procedures, is intended as an operating manual for general use of the system. Under ideal experimental conditions, the spatial resolution of the counters is about 1 to 1.5 mm (FWHM), dependent on the energy loss of the incident particle in the counter. The spatial response of the counters is linear to within 0.5% of the active length. Furthermore, the system contains a conventional proportional counter, behind the position counter, designed to provide particle identification based on the energy lost in the counter. Pulses from the two counters are normally analyzed in coincidence to provide excellent particle discrimination. Examples of typical experimental results are also presented.

A novel design concept for a "flashlight-type" in-core thermionic reactor is described. This concept, called the "double-sheath" design in contrast to the previously considered "wet-sheath" and "dry-sheath" concepts, permits the build-up of high reactor output voltages, without the danger of cesium breakdown and shorts-to-ground. In addition to a description of the design and its functional components, a brief discussion of suggested fuel element fabrication and reactor assembly techniques is presented. The proposed design offers the potential of high reliability because only insulators at very low potentials (e.g.<3 volts) are in contact with cesium vapor; because there are no ceramic or cermet seals within the reactor (all are outside, beyond the reflectors); and because all vacuum-tight joints in the reactor are between ductile niobium components.

A method for electronically temperature-flattening a "flashlight-type" thermionic reactor with both axial and radial heat generation nonuniformities is described. The method, which makes use of compensating electron cooling variation while satisfying the voltage- and current-matching constraints on the in-core series-parallel diode network, results in substantially uniform emitter temperatures throughout the reactor. Novel analytical techniques for temperature-flattening a nonuniform reactor are described and used to generate specific illustrative designs. It is shown that, even with severe nonuniformities, the temperature-flattened reactor exhibits almost as high a power density and conversion efficiency as a reactor using fuel-zoning for full power flattening. By eliminating the need for fuel-zoning, the concept described here reduces the critical size and system weight, and permits the use of thicker emitter walls for enhanced reliability.

Scrap status reports requested by P.A. Craig of the Nuclear Materials Management Branch on July 14, 1972 are presented. The additional detail required disclosed the enriched uranium covered by the scrap declaration HYA-15 was not reported as scrap on the June 30 COEI Reports.

This report was compiled at the Hanford Engineering Development Laboratory operated by Westinghouse Hanford Company, a subsidiary of Westinghouse Electric Corporation, for the United States Atomic Energy Commission, Division of Reactor Development and Technology, under Contract No. AT (45-1) 2170. It describes technical progress made in the Interlaboratory LMFBR Reaction Rate Program during the reporting period. The Interlaboratory LMFBR Reaction Rate (ILRR) program has been established by USAEC/RDT to develop a capability to accurately measure neutron-induced reaction rates for LMFBR fuels and materials development programs. The initial goal for the principal fission reactions, {sup 235}U, {sup 238}U, and {sup 239}Pu, is an accuracy to within {+-}5 at the 95% confidence level. Accurate measurement of other fission and non-fission reactions will be required, but to a lesser accuracy, between {+-}5 to 10% at the 95% confidence level. A secondary program objective is improvement in knowledge of the nuclear parameters involved in fuels and materials dosimetry measurements of neutron flux, spectra, fluence, and burnup. These accuracy goals for the ILRR program are severe; measurements of fast-neutron-induced reaction rates have not been rapidly moving toward this level of precision. Using a number of techniques in well established neutron environments of current interest for …