States

Application of the Variational Method to the Calculation of the Time Dependence of the Neutron Flux in Small Pulsed Slabs, Cylinders and Spheres (open access)

Application of the Variational Method to the Calculation of the Time Dependence of the Neutron Flux in Small Pulsed Slabs, Cylinders and Spheres

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.
Date: December 16, 1963
Creator: Judge, F. D. & Daitch, Paul B. (Paul Bernard), 1925-
Object Type: Report
System: The UNT Digital Library
Doppler Broadening of the Total, Fission, Capture, and Scattering Neutron Cross Sections of Pu-241 (open access)

Doppler Broadening of the Total, Fission, Capture, and Scattering Neutron Cross Sections of Pu-241

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.)
Date: December 16, 1963
Creator: Marshall, N.H. & Simpson, O.D.
Object Type: Report
System: The UNT Digital Library
Evaluation of Resonance Capture Approximations (open access)

Evaluation of Resonance Capture Approximations

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.
Date: December 16, 1963
Creator: Edgar, K. R.
Object Type: Report
System: The UNT Digital Library
Hanford Laboratories monthly activities report, November 1963 (open access)

Hanford Laboratories monthly activities report, November 1963

This is the monthly report for the Hanford Laboratories Operation, November 1963. Metallurgy, reactor fuels, chemistry, dosimetry, separation processes, reactor technology, financial activities, visits, biology operation, physics and instrumentation research, and employee relations are discussed.
Date: December 16, 1963
Creator: unknown
Object Type: Report
System: The UNT Digital Library
Production test IP-644-D fuel surface crud monitor irradiation (open access)

Production test IP-644-D fuel surface crud monitor irradiation

The objective of this test is to demonstrate and evaluate the design of the proposed N-Reactor fuel surface crud monitor to be used in the N Reactor.
Date: December 16, 1963
Creator: Neidner, R.
Object Type: Report
System: The UNT Digital Library
Requirements for Military Radiacs: [Part] 2. Effect of the Operator on the Energy-Directional Response of Portable Radiation Instruments (open access)

Requirements for Military Radiacs: [Part] 2. Effect of the Operator on the Energy-Directional Response of Portable Radiation Instruments

"This report presents the results of experiments designed to determine the response of selected military high-range radiacs to extended gamma radiation fields with and without a phantom (simulated operator)." (from Abstract)
Date: December 16, 1963
Creator: Wasson, H. R. & Williams, D. H.
Object Type: Report
System: The UNT Digital Library
Tension properties of tie rods. Part No. 944C732 spec. grade. Quality control request No. 274 (open access)

Tension properties of tie rods. Part No. 944C732 spec. grade. Quality control request No. 274

None
Date: December 16, 1963
Creator: Allison, H. & Zibritosky, G.
Object Type: Report
System: The UNT Digital Library
ACTIVITY RELEASE FROM THE N.S. SAVANNAH IN THE MAXIMUM CREDIBLE ACCIDENT (open access)

ACTIVITY RELEASE FROM THE N.S. SAVANNAH IN THE MAXIMUM CREDIBLE ACCIDENT

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)
Date: October 16, 1963
Creator: Anderson, T. D.; Buchanan, J. R.; Cottrell, W. B.; Fontana, M. H.; Klepper, O. H. & McCurdy, H. C.
Object Type: Report
System: The UNT Digital Library
Chemistry of Isotopes (open access)

Chemistry of Isotopes

None
Date: October 16, 1963
Creator: Bigeleisen, J.
Object Type: Report
System: The UNT Digital Library
Corrosion of Stainless Steel in Acidic Nitrate Waste Solutions From Processing Stainless Steel Reactor Fuels (open access)

Corrosion of Stainless Steel in Acidic Nitrate Waste Solutions From Processing Stainless Steel Reactor Fuels

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 …
Date: October 16, 1963
Creator: Hess, D. N.; Rice, L.; Willis, B.; Snavely, E. S. & Clark, W. E.
Object Type: Report
System: The UNT Digital Library
MICROPROBE STUDY OF BRAZED JOINT FOR SNAP 10A THERMOELECTRIC PUMP APPLICATION (open access)

MICROPROBE STUDY OF BRAZED JOINT FOR SNAP 10A THERMOELECTRIC PUMP APPLICATION

There is a program requirement to produce sound brazed joints between stainiess steel and copper metal components that will remain sound after long time exposure to a high vacuum environment at a temperature of approximately 1000 deg F. Results are described of a microprobe study of one of the promising brazed joints after long time exposure to high vacuum conditions at a temperature of approximately 1200 deg F. It was desired to determine the extent of gold diffusion into the stainless steel after long time exposure under accelerated conditions. The brazing test alloy contained 81.5% gold, 15.5% copper, and 3.0% nickel. Microprobe scan photographs are shown for each of the major elements present in the test specimen and a traverse profile sketch of the braze zone is shown for the microprobe equipment set to detect gold and nickel. The results of this microprobe study indicated significant diffusion of gold into the copper metal but no diffusion of gold into the stainless steel. There were indications of minor diffusion of nickel into the copper and perhaps some concentrating of nickel atoms at the surface of the stainless steel. (auth)
Date: October 16, 1963
Creator: Reed, E.L.
Object Type: Report
System: The UNT Digital Library
STUDIES IN CONTACT MICRORADIOGRAPHY (open access)

STUDIES IN CONTACT MICRORADIOGRAPHY

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.
Date: October 16, 1963
Creator: McClung, R. W.
Object Type: Report
System: The UNT Digital Library
Texas Attorney General Opinion: C-162 (open access)

Texas Attorney General Opinion: C-162

Document issued by the Office of the Attorney General of Texas in Austin, Texas, providing an interpretation of Texas law. It provides the opinion of the Texas Attorney General, Waggoner Carr, regarding a legal question submitted for clarification: The number of sets of ballot forms, ballot boxes, returns, etc., required for the special elections to be held in Travis County on November 9, 1963.
Date: October 16, 1963
Creator: Texas. Attorney-General's Office.
Object Type: Text
System: The Portal to Texas History
Thermodynamic Properties and Phase Relationships in the U-C System and Selected U-M-C Systems (open access)

Thermodynamic Properties and Phase Relationships in the U-C System and Selected U-M-C Systems

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)
Date: October 16, 1963
Creator: Farr, J. D. & Bowman, M. G.
Object Type: Report
System: The UNT Digital Library
Corrosion Mechanisms in Refractory Metal-Alkali Metal Systems (open access)

Corrosion Mechanisms in Refractory Metal-Alkali Metal Systems

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 …
Date: September 16, 1963
Creator: DiStefano, J.R. & Hoffman, E.E.
Object Type: Report
System: The UNT Digital Library
Fuel Failure Examinations and Analyses in the High Power Density Program (open access)

Fuel Failure Examinations and Analyses in the High Power Density Program

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 …
Date: September 16, 1963
Creator: Arlt, W. H. & Vandenberg, S. R.
Object Type: Report
System: The UNT Digital Library
Hanford Laboratories monthly activities report, August 1963 (open access)

Hanford Laboratories monthly activities report, August 1963

This is the monthly report for the Hanford Laboratories Operation, August 1963. Metallurgy, reactor fuels, chemistry, dosimetry, separation processes, reactor technology, financial activities, visits, biology operation, physics and instrumentation research, and employee relations are discussed.
Date: September 16, 1963
Creator: unknown
Object Type: Report
System: The UNT Digital Library
Diffusion Parameters of Water for Various Scattering Kernels (open access)

Diffusion Parameters of Water for Various Scattering Kernels

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.
Date: August 16, 1963
Creator: Calame, Gerald P.
Object Type: Report
System: The UNT Digital Library
Electron Optical Studies of Low-Pressure Gases (open access)

Electron Optical Studies of Low-Pressure Gases

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."
Date: August 16, 1963
Creator: Marton, L.; Schubert, David C. & Mielczarek, S. R.
Object Type: Report
System: The UNT Digital Library
K and N reactor capabilities (open access)

K and N reactor capabilities

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.
Date: August 16, 1963
Creator: Lang, L. W. & Dowis, W. J.
Object Type: Report
System: The UNT Digital Library
KER-2 tube history (open access)

KER-2 tube history

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.
Date: August 16, 1963
Creator: Banister, W. C.
Object Type: Report
System: The UNT Digital Library
Mass-Spectrometric Study of the Ruthenium-Oxygen System (open access)

Mass-Spectrometric Study of the Ruthenium-Oxygen System

None
Date: August 16, 1963
Creator: Norman, J. H.; Staley, H. G. & Bell, W. E.
Object Type: Report
System: The UNT Digital Library
Old and New Problems in the Field of Vapor-Liquid Equilibria (open access)

Old and New Problems in the Field of Vapor-Liquid Equilibria

A review is presented on vapor-liquid equilibria. Arnong the topics discussed are activity coefficients, consistency criteria, automatic computation, and gaseous mixtures. A bibliography of 18 references is included. (D.L.C.)
Date: July 16, 1963
Creator: Redlich, O.
Object Type: Article
System: The UNT Digital Library
PROCESSING OF MULTI-CHANNEL-ANALYZER NUCLEAR REACTION SPECTRA WITH THE NEWDAC PROGRAM (open access)

PROCESSING OF MULTI-CHANNEL-ANALYZER NUCLEAR REACTION SPECTRA WITH THE NEWDAC PROGRAM

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)
Date: July 16, 1963
Creator: Ball, J.B.
Object Type: Report
System: The UNT Digital Library