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The release of fission products that would occur following the maximum credible accident aboard the N.S. Savannah has been examined. Four significantly different, but realistic, operating histories were considered. The rate of release of noble gases and of iodine isotopes as a function of time after the accident was determined for each operating history and for both normal and emergency reactor-compartment ventilation systems. The influence of radioactive decay and of the time delay in release and transport of activity through the containment system was investigated. Most of the results are expressed in terms of activity release and resultant individual exposures, although some consideration is given to population exposures and to the interpretation of these results in the light of stationary reactor site criteria. (auth)

Summary: The High Power Density Project includes a comprehensive fuel development program which has the objective of developing and demonstrating the performance of a nuclear reactor core having a high power density, long fuel life, and low fabrication cost. The fuel program is made up of two principal tasks. Task 1A consists of irradiation tests in the VBWR of Type 304 stainless steel clad, UO2 pellet type fuel rods fabricated by current commercial processes. Task 1B consists of the investigation of lower cost fabrication processes and the irradiation testing of fuel elements fabricated by these processes. Both tasks include the investigation of the feasibility and use of thin-wall stainless steel cladding as a means of improving the neutron economy and fuel cycle costs of stainless steel clad fuel. Irradiation of the Task 1A fuel assemblies in the VBWR was initiated in September, 1960. Subsequently, Task 1B fuel assemblies were inserted in the VBWR as various fabrication processes and design concepts were investigated. Fuel cladding failures have occurred in fuel rods in both Task 1A and 1B. As of this date, cladding failures have occurred in twenty-two rods of approximately 700 fuel rods which have been irradiated. Twenty of the failures …

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)

Zirconium process tube No. 1986 was installed in KE Reactor tube channel No. 2864 on April 16, 1959. This report describes the history and the conditions to which it was exposed during its residence in the reactor. The tube was removed on May 31, 1963.

Extraction of the external beam of the cosmotron with maximum efficiency and minimum duration for measurements of the magnetic moment of the lambda hyperon requires addition of a rapid beam ejector (RBE). Early experiments with the RBE give lower ejection efficiency than the standard ejection system. Reconstruction of the RBE with lengthening of the rise time of the system gives improved values. Computer studies that involve solving the equation of motion for the radial betatron oscillation with time increasing perturbation in one section yield information on particle distributions and result in increases of the turn spacings in RBE to prevent betatron oscillation distribution distortions. Ejection efficiency is now the same with and without the RBE. (D.C.W.)

>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 …

The basic assumption of the Serber model in the description of high- energy nuclear reactions is that the interactions of incident particles with complex nuclei can be described in terms of individual particle-particle collisions within the nucleus. Calculations were performed making use of the basic assumption of the Serber model, a more realistic nuclear model, recent cross-section data, and an exact statistical sampling technique. The sampling technique has not been used previously in calculations of this type. Calculations were performed for incident e (as Fe/sup 59 /sup +/, e (as Fe/sup 59 /sup -/, neutrons, and protons on nuclei from lithium to uranium. The energy range of the incident particles varied from about 50 to 350 Mev, i.e., the energy region in which pion production is not likely. Free-particle cross sections were used in determining the collisions within the nucleus, and statistical sampling techniques were used throughout, The problem was coded for the IBM-7090. Extensive comparisons with experiment were made and the results indicate that the calculation can be used to predict most of the cascade data for incident nucleons on complex nuclei, but only the gross features of the data are predictable for incident pions on nuclei. The effects …

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Abstract. Some diffusion parameters of water are computed with various thermal-neutron scattering laws. It is found that the diffusion cooling coefficient, in particular, is reasonably sensitive to the scattering law, but that the diffusion cooling coefficients predicted by the Radkowsky and Nelkin kernels are in fortuitious agreement. The coefficients computed for the Nelkin kernel, when treated in a manner consistent with the way in which experimental data are treated, are in reasonable agreement with the results of a recent experiment.

Report issued by the Oak Ridge National Laboratory discussing a Health Physics Instrument Manual. Descriptions, characteristics, and applications of different instruments are presented. This report includes tables, illustrations, and photographs.

The use of liquid metals introduces solid-liquid metal interactions which are not primarily electrochemical, as found in systems involving aqueous raedia. The corrosion of solid metals by these coolants occurs as the system attempts to attain chemical equilibrium. The mechanisms by which this can occur are (a) dissolutioning, which results from the solubility relationships between the solid and liquid metals, and (b) impurity reactions, resulting from the presence of interstitial impurities, such as oxygen, nitrogen, and carbon, in the solid and liquid metals. The manner in which dissolutioning proceeds gives rise to many types of attack ranging from simple solution to mass transfer of one or more constituents of an alloy. Some variables which influence the rate and type of dissolutive corrosion are: temperature, flow velocity, surface area to volume ratio, surface condition of solid metal, temperature gradient, and number of materials in contact with the same liquid metal. The refractory metals tungsten, molybdenum, tantalum, and niobium, as well as other high-melting bodycentered cubic metals, have excellent resistance to dissolutive attack by the alkali liquid metals at high temperatures. However, there are numerous occasions when it is desirable to utilize the unique capabilities of several structural materials in the same …

The program KRUDE, which solves the slowing down and adjoint equations for a mixture of resonance and nonresonance isotopes in an infinite homogeneous medium, was used to evaluate some resonance capture approximations (variational and successive) that use linear combinations of narrow and wide resonance fluxes. Results obtained for resonance capture in the 291-ev resonance of Zr/sup 91/ and the 192-ev resonance of U/sup 238/ are compared, and three methods for including Doppler effects in the variational method are considered.

Results of phase and thermodynamic studies strongly suggest only small differences in stability for the different uranium carbides. Partial phase diagram studies are made on several U--M--C ternary systems. Studies of the U-- Zr-- C and the U--Nb--C system indicate improved physical properties and stability for (U,M)C solid solutions in some reactor fuel applications. A relatively large number of compounds of the type UMC/sub 2/ exist and may exhibit desirable properties as specific reactor fuels. For example, UMoC/sub 2/ does not hydrolyze and does not react with C to form UC/sub 2/. (auth)

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The influence of the surface state on steel corrosion in high temperature steam and water is studied. The autoclave tests were continued for stainless steel grade 304 and undertaken for Creusot 1.2 MD07 boilerplate steel. Regarding the stainless steel, complete results for the tests in water at 300 deg C and partial results for the tests in steam at 400 deg C--200 kg/cm/sup 2/ are presented. The evaluation of the corrosion by ponderal variations involves the reduction of the adhering oxides by hydrogen at 800 deg C. Tests in water at 300 deg C reveal the favorable character of the Jacquet bath electrolytically polished state. Corrosion is lowered by a factor of about 3 compared with the rough or fine machined or mechanically polished with 600 paper under water states. The advantages that are acquired by the electrolytically polished state cannot be appraised by autoclave tests, as the corrosion rate tends to cancel itseif out after a period of time which depends on the surface state. It was revealed that 8 weeks was suitable for classifying the various surface states. In steam at 400 deg C--200 kg/cm/sup 2/, it is observed that the electrolytically polished state is a disadvantage. The …

The purpose of this document is to describe an engineering program being conducted by Reactor Design, Facilities Engineering Section to provide a solution for current and anticipated problems of binding and inoperative horizontal control rods (HCR`s) at the ``K`` Reactors. Primary emphasis in the program is On alleviating problems at the K Reactors because of the more advanced stage of graphite distortion and hence control rod problems existing at the K Reactors as compared to the other reactors. It is recognized, however, that problems of similar severity can reasonably be anticipated at the other reactors in the near future. With this in mind, design of remedial measures for K will incorporate consideration of adaptability to the other reactor HCR systems. Also, primary concern of this program is to provide an HCR system which will fulfill functional requirements for safe operation of the reactors at current power levels under conditions of severe HCR channel distortion. Suitability of the system for producing by products such as tritium is considered to be of secondary importance at this time although still a point to be kept in mind in designing the new rod tip and to be studied in detail at a later date.

One capsule containing BeO-30 vol% UO/sub 2/ fuel pellets was irradiated to a uranium burnup of approximately 30,000 Mwd/t. The results of a microscopic examination and physical measurements made during the hot-cell examination of the capsule were described. (auth)

The variational method is applied to the monoenergetic time dependent transport equation to obtain a simple relation for the asymptotic decay constant in small pulsed assemblies. The results indicate that flat trial functions may be a reasonable representation of the flux distributions in the thin slab limit. This approach is superior to many of the usual transport approximations.

This report contains data on the relative capabilities of the K and N plants to produce various isotopes. The data are ``direct and quantitative`` in cases where production plans for the various isotopes have been studied. For isotope studies not completed production capabilities are, of necessity, discussed from only a qualitative standpoint.

ABS>The cross sections were calculated by the Reich-Moore multilevel formula from 0.02 to 11 ev and were convoluted with Doppler functions corresponding to various sample temperatures. The cross sections are tabulated vs neutron energy for temperatures of 27, 500, 1000, 2000, and 3000 deg C. (D.C.W.)

From Abstract: "This document is the final report of research carried on in the Electron Physics Section of the National Bureau of Standards during the period from February 1, 1955 to March 1962 in developing an electron optical method for the visualization of low-pressure gas flow."

Recent developments in techniques for low-voltage radiography have found application for the examination and evaluation of minute details in small or thin specimens. Utilization of x-ray tubes and helium chambers with thin windows for maximum transmission of soft x rays and bare film with dark-room exposure techniques have allowed very high contrast radiographs to be produced on low-contrast materials. These conditions, coupled with very high resolution photographic emulsion detectors, have resulted in the observation of detail approximately 1 {micron} in size. Useful examination of the plates and subsequent reproductions have been made at magnifications as high as 500X. This contact system offers the advantage of evaluation of a relatively large area, as compared to the restricted field of observation of projection microradiography. Included among the subjects have been graphite-coated UC{sub 2} particles, graphite, beryllium, paper, and other organic specimens.

Technical report. From Abstract : "A number of imaging furnace systems and sources are discussed with emphasis on the carbon arc image furnace. Several potential applications of the carbon arc image furnace in high temperature research are described and a new method of heat capacity determination is discussed."