A method is described for obtaining an approximate solution to the equations describing a nucleon-meson cascade by using the angular dependence of the secondary particle production kernels as a perturbation. The usefulness of the method lies in the fact that in a slab geometry the equations that must be solved numerically are essentially the same as those that are used in the straight-ahead approximation and have been solved previously. (auth)

The scintillation camera is a nonscanning instrument for displaying the distribution of radioactive isotopes. It can be used, for example, to show abnormalities in the thyroid gland with I-131, the size, shape and location of kidneys with Hg-203 Neohydrin or to locate brain tumors either with Hg-203 Neohydrin or with the new positron emitting agent, Ga-68 EDTA. For many applications, the scintillation camera has higher sensitivity than conventional isotope scanners, and will produce pictures in less time or with a smaller quantity of isotope present. Alternatively, it produces better pictures if the conventional dosage and exposure factors are retained. Because of the short exposure time, and because the scintillation camera is continuously sensitive to all areas within its field of view, it is well adapted to taking rapid sequences of still pictures or time-lapse motion pictures of subjects in which the distribution of radioactivity is changing. For example, time lapse pictures have been taken showing I-131 Rose Bengal Bengal being excreted from the liver of children with liver disease and of I-131 hippuran going through the kidneys of patients suspected of kidney disease.

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The dissociation of various mixtures of hydrogen and water vapor and of cupric oxide was calculated over a wide range of temperatures (from 600 to 1700 deg C for the H/sub 2/--H/sub 2/O system, and from 200 to 1000 deg C for CuO). The resulting partial pressures of oxygen are presented in tabular form. (auth)

A FORTRAN program is presented for processing pulse-height data for particles emitted from a nuclear reaction. The program corrects the particle energy for any absorber preceding the detector and computes the differential center-of-mass cross section as a function of the reaction Q value and the excitation energy of the final nucleus. The energies can be computed either relativistically or nonrelativistically. The program is written as a series of subroutines to facilitate possible expansion of the program and to allow easy accommodation of different data input routines. The output of the program is printed in tabular form and, at the discretion of the user, punched on cards for off-line plotting or for input to other programs. (auth)

>The corrosion resistance of mantensitic and ferritic austenitic stainless steels and carbon steels in pressurized water at 500 to 600 deg F is compared. Included are specific out-of-pile data for austenitic stainless steels, AISI types types 410, 420, 431, and 440C; the ferritic AISI types 430, 442, and 446; the precipitation-hardening type 17-4PH; and carbon steels, ASTM 212 A and B. Available corrosion results obtained under irradiation at exposures in the range of 7 x 10/sup 16/ to 3 x 10/sup 19/ nvt are also included for types 304, types of martensitic and ferritic stainless steels which were evaluated do not contain nickel. For application where it is desirable to minimize Co/sup 58/ activity produced from nickel, selection of a martensitic or ferritic stainless steel may be more appropriate than choosing the more popular nickel-bearing austenitic stainless steel or a fuel-element cladding material. Interpretation of the data indicates that, on the average, martensitic and ferritic stainless steels corrode more rapidly than austenitic alloys but more slowly than carbon and low-alloy steels. Under selected controlled water conditions or under irradiation, the corrosion of the nickel-free stainless steels appears to differ little from the austenitics. The corrosion of martensitic and ferritic stainless …

From introduction: This report presents the results of a study of large nuclear reactor systems for supplying energy for the distillation of sea water.

The DCX-2 is a large, complex experimental apparatus. Its aim is the generation of a hot, dense plasma by the injection and dissociation of 600-kev hydrogen molecNoneular ions in a magnetic-mirror field. For facilitating this process, the molecular ions are given a long path in the machine, and the ion- pumping action of the plasma is used to maintain the vacuum. The major component systems of the apparatus are the ion source and accelerator, highvoltage power supply, magnet system, beam-injection duct, vacuum system, and dissociating arc. The design, construction, and performance of each component system, the constructional features not peculiar to any one component, and the instruments and techniques available for plasma study are described. (auth)

This review includes a discussion of many methods for detecting ultrasonic images with emphasis upon the problems involved in a nondestructive inspection system employing ultrasonic imaging techniques. The detection methods are compared from the standpoint of threshold sensitivity. It is concluded that a system which will respond to an ultrasonic intensity of 10/sup -3/ w/cm/sup 2/ or less will probably be necessary for a practical nondestructive inspection system. The detection methods which meet this requirement include those classified as optical and mechanical, and as electronic. The annotated bibliography includes 74 entries, many of which contain more than one reference. Included in this bibliography are references to most of the known methods for ultrasonic imaging. (auth)

Data are presented that show a marked species difference in the degree of damage and in the course of events seen in the bone marrow and peripheral blood after a given dose of radiation. The data taken together indicate strongly, but do not prove, that the picture seen results primarily from damage to the stem cell population. This damage to the stem cells is manifested later in the more mature differentiating cells of the marrow, and in the peripheral blood. The picture seen results both from death of stem cells, and also injury leading to reduced proliferative capacity, with later death of the injured stem cell and all of its progeny. Thus the picture seen is a result of both quantitative and qualitative changes resulting directly from the exposure of the stem cells, and species differences relative to sensitivity and time course of events appear to depend to a large degree on differential sensitivity of the bone marrow stem cell populations to death and injury. (auth)

Research on a welding process for closing the ends of pathfinder fuel elements is reported. Optimum parameters for certain variables (amperage, weld travel, preheat, etc.) affecting weld quality were determined, and two modified end cap designs were investigated and found to reduce weld sensitivity to certain variables. Use of chills on the fuel tube greatly improved weld puddie geometry and microstructure. Optimum weld parameters for rods containing UO/sub 2/ fuel were experimentally established. (D.C.W.)

This report is an explanation of the response characteristics, some typical curves of displacements, velocities, etc., and the computer circuit diagram.

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Calculations of the photonuclear giant resonance according to the Wilkinson model are presented in this report. In this model the giant resonance in the cross section for absorption of gamma rays by nuclei is ascribed to the excitation of large numbers of nucleons in closed shells. The model generally predicts correctly the integrated cross section for the giant resonance, bu the resonance energy is too low. Results are presented in a series of tables and formulas so that the integrated cross section may be calculated for any given nucleus.

The theoretical development, statistical treatment, and application of hot channel factors in compact SNAP reactors as represented by the SNAP 8 experimental core loading are presented. The channel and rod power effects of variation in the concentrations of uranium, hydrogen, and poison in the fuel rods are given. The statistical distributions of all variables are examined. A random selection of rods and channels is compared to the actual SNAP 8 configuration, with no difference noted. Confidence limits are set on hot rod and hot channel factors. Various other factors and aspects of the problem are discussed. The results of the study showed that the hot channel factors may be reduced to less than +2% over the nominal power, as opposed to a hot channel factor of about +10% as previously determined by empirical methods. (auth)

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From abstract: "Study of radiation effects upon the tensile properties of the alloys, corrosion behavior in the absence and presence of stress, effect of prolonged, high temperature exposures upon structure sensitive properties of the alloys, and physical metallurgical changes as a function of exposure in a superheat environment.

Irradiation of Np-237 in Hanford reactors and recovery of the Pu-238 product in a close-coupled separations plant is currently of interest. Such a concept has the potential of increasing in Pu-238 production rates. The results of initial calculations on the subject are presented herein to aid further study and evaluation. Much of the information is presented in terms of the aqueous target system proposed in earlier work (i.e., irradiation and processing of an aqueous neptunium solution). However, most of the information can be converted for evaluation of a solid target system.

Studies were made on the kinetics of the polymerization of tetravalent Pu, depolymerization of polymeric Pu(IV), and properties of Pu(IV) poiymer under representative solution conditions of acidity, temperature, and ion concentrations encountered in fuel processing. The polymerization of tetravalent Pu was studied as a function of the Pu concentration, (1 to 8 mg Pu/ml), nitric acid concentration, (0.03 to 0.3 M), and temperature (25 to 95 deg ). Under these conditions, disproportionation and nitrate oxidation of the tetravalent Pu occurred and were also studied. It is clearly indicated that colloidal polymer formation is favored by an increase in the Pu concentration and temperature, or by a decrease in the acidity. Temperature had a pronounced effect on the rate and extent of polymer formation at any particular acidity. The effects of UO/sub 2/(NO/sub 3/)/sub 2/, Al(NO/sub 3/)/sub 3/, NaNO/sub 3/, and F/sup -/ upon the kinetics of polymer formation in acidic nltrate media were also determined at low acidities and elevated temperatures. In the presence of high concentrations of the nitrate salts the colloidal Pu(IV) polymer was observed to precipitate. The precipitation of aged colloidal Pu(IV) polymer by nitratecontaining electrolytes, HNO/sub 3/, Al(NO/sub 3/)/sub 3/, NaNO/sub 3/, and LiNO /sub 3/, …

The Spert IV facility, the initial critical experiment, the initial core, the operational core loading, and core parameter measurements (void and temperature coefficients, control rod worth, neutron flux distributions, etc.) made before initiation of the kinetics testing program are described. (auth)

Many measurement of neutron spectra have been made in water assemblies. In these system a large part of the spectrum is given by an essentially Maxwellian distribution at the moderator temperature which is insensitive to the scattering model. Hence, the test of the energy exchange scattering kernel is in the difference of the spectrum and the fundamental or Maxwellian component. The figure shows the spectrum for the Nelkin model. Once the fundamental has been subtracted neither theoretical model seems to fit the data extremely well. Below kT the Nelkin model is a closer fit than the gas model but it underestimates the deviation from the Maxwellian whereas in the joining region it overestimates the distortion.

The nuclear heat generation rate in the first capsule irradiated was higher by a factor of two than was calculated. The original capsule was irradiated in a dry bore with cooling water in the annulus only. The new capsule will be irradiated in a water-cooled bore facility with additional cooling coils around the lithium containing tube. This will keep the inner capsule temperature below 150 C during the initial tritium buildup period prior to outgassing. This Supplement authorizes the irradiation of an additional capsule and the removal of the present facility and installation of a single tube general purpose facility. All remaining provisions of the original development test are in force except for minor exceptions due to the water flow in the bore which have been changed in the following writeup.

This report is on Opinion of Supreme Court on Reading Bible.

A set of 23-group neutron cross sections for use in the calculation of neutron thermalization and thermal neutron spectral effects in SNAP reactors is compiled. The sources and methods used to obtain the cross sections are described. (auth)