Nuclear metallurgy lectures: Chapter 5 (open access)

Nuclear metallurgy lectures: Chapter 5

In a preceding lecture all the components necessary to secure a controlled nuclear chain reaction were discussed. The business at Hanford is to use these components in the most efficient manner possible to manufacture the desired products of irradiation - the primary product being Pu. In this lecture of the variables of such operation are considered.
Date: May 13, 1955
Creator: Lang, L. W.
System: The UNT Digital Library
Nuclear metallurgy lectures. Chapter 6, Reduction of uranium (open access)

Nuclear metallurgy lectures. Chapter 6, Reduction of uranium

This report consists of Chapter Six of the Nuclear Metallurgy Lectures. Chapter six discusses the reduction of uranium, chemical composition of uranium ores, extraction process for uranium ores, bomb reduction, green salt, and dingots.
Date: May 26, 1955
Creator: Kattner, W. T.
System: The UNT Digital Library
Nuclear metallurgy lectures. Chapter 9, Fabrication and heat treatment of uranium (open access)

Nuclear metallurgy lectures. Chapter 9, Fabrication and heat treatment of uranium

This chapter presents the highlights of the fabrication and heat treatment of uranium with emphasis on HAPO type core material. For pile use three properties of uranium are of prime interest; grain size, type and degree of preferred orientation, and the mechanical properties.
Date: May 12, 1955
Creator: Riches, J. W.
System: The UNT Digital Library
Nuclear metallurgy lectures. Chapter 12, Effect of irradiation on the properties of fissionable and non-fissionable materials (open access)

Nuclear metallurgy lectures. Chapter 12, Effect of irradiation on the properties of fissionable and non-fissionable materials

This report summarizes the effect of irradiation on the properties of fissionable and non-fissionable materials. General property changes, irradiation of zirconium, zirconium-tin alloys, the irradiation of aluminium, irradiation of thorium and uranium, are a few of the topics discussed.
Date: May 25, 1955
Creator: Hueschen, R. E.
System: The UNT Digital Library
Nuclear metallurgy lectures, Chapter 17 (open access)

Nuclear metallurgy lectures, Chapter 17

This chapter covers process tubes; it is divided into: philosophy of safety factors, mechanical properties of available materials (C steel, mo steel, Cr-Mo steel, ss-304, ss-347), and costs (zircaloy-2).
Date: May 18, 1955
Creator: unknown
System: The UNT Digital Library
Operating conditions of the ORR cooling system at 20 Mw (open access)

Operating conditions of the ORR cooling system at 20 Mw

None
Date: May 23, 1955
Creator: Sanders, J P
System: The UNT Digital Library
OPERATION UPSHOT-KNOTHOLE Project 6.12 DETERMINATION OF HEIGHT OF BURST AND GROUND ZERO (open access)

OPERATION UPSHOT-KNOTHOLE Project 6.12 DETERMINATION OF HEIGHT OF BURST AND GROUND ZERO

The purpose of this series of experiments was to test methods available to the field army for tactical determination of atomic burst location and yield over enemy-held terrain. Preliminary analysis indicated that the systems that should be tested were sound ranging, seismic height of burst determination, photographic flash ranging, and Bhangmeter type systems for yield determination. Sound ranging was accomplished using standard equipment with modified techniques. Microphone arrays of dimensions which were small compared to the range were used to eliminate hyperbolic curvature corrections and to simplify meteorological corrections. A new system of meteorological corrections was employed. This system was based on approximating the maximum height reached "by the sound vhich ultimately passes across the microphone array. It was determined that this technique gave far greater accuracy than conventional techniques at these long ranges. Most accurate locations were obtained on air bursts. For air bursts at ranges from 20,000 to 60,000 meters, angular standard deviations of 13.8 minutes of arc were obtained. For air bursts, the average radial location error expressed as per cent of range was 0.61 per cent. It was estimated that in a tactical situation these locations could he computed in less than 30 minutes. Seismic height …
Date: May 1, 1955
Creator: Tiede, Roland V.; Kelly, Daniel F. & Burger, Kenneth C.
System: The UNT Digital Library
Permissible Rate of Temperature Rise of Shells (open access)

Permissible Rate of Temperature Rise of Shells

None
Date: May 26, 1955
Creator: Greenstreet, B. L. & Thompson, A. S.
System: The UNT Digital Library
Potential Measurements of Aluminum-Clad Uranium Systems (open access)

Potential Measurements of Aluminum-Clad Uranium Systems

None
Date: May 1, 1955
Creator: Tripler, A. B., Jr.; Beach, J. G. & Faust, C. L.
System: The UNT Digital Library
PRELIMINARY CRITICAL TESTS USING AQUARIUM FUEL ELEMENTS IN THE BSR GRID (open access)

PRELIMINARY CRITICAL TESTS USING AQUARIUM FUEL ELEMENTS IN THE BSR GRID

None
Date: May 31, 1955
Creator: Henry, K M; Johnson, E B & Maienschein, F C
System: The UNT Digital Library
PRELIMINARY LABORATORY EVALUATION OF AN ELECTRODIALYTIC METHOD FOR THE TREATMENT OF RADIOACTIVE WATERS (open access)

PRELIMINARY LABORATORY EVALUATION OF AN ELECTRODIALYTIC METHOD FOR THE TREATMENT OF RADIOACTIVE WATERS

None
Date: May 18, 1955
Creator: Seal, M S & Pecsok, D A
System: The UNT Digital Library
PRINCIPLES AND TECHNIQUES OF ULTRASONIC INSPECTION (open access)

PRINCIPLES AND TECHNIQUES OF ULTRASONIC INSPECTION

None
Date: May 23, 1955
Creator: Psillas, H.C.
System: The UNT Digital Library
Process development review (open access)

Process development review

This report discusses process development programs to be reviewed at the Savannah River Laboratory. The review will include reactor and metallurgical process development programs and chemical processing development programs.
Date: May 17, 1955
Creator: Evans, L. C.
System: The UNT Digital Library
PT-105-600-A: First measurement of graphite temperature reactivity coefficient at KE (compilation of data) (open access)

PT-105-600-A: First measurement of graphite temperature reactivity coefficient at KE (compilation of data)

This test consisted of a series of helium purges of the pile gas atmosphere to bring the helium content up to about 70 to 80% helium followed by a series of CO{sub 2} purges to restore the pile atmosphere to its initial composition. The purges where spaced roughly four hours apart to enable the reactor to reach a steady temperature before purge was undertaken. The test results are presented in this report.
Date: May 13, 1955
Creator: Gumprecht, R. O.
System: The UNT Digital Library
A Pulsed Eddy Current Technique for Measuring Clad Thickness. Metallurgy Program 12.1.2 (open access)

A Pulsed Eddy Current Technique for Measuring Clad Thickness. Metallurgy Program 12.1.2

A pulsed eddy current technique for measuring the cladding thicknesses of reactor fuel elements is described. Special emphasis has been put on the measurement of zirconium cladding. In this technique an electromagnetic field is applied at the surface of the clad fuel element by means of a probe coil. Whenever the waves enco nter a sudden discontinuity, such as an interface,''echoes'' are produced. The same probe coil is used for sending the electromagnetic radiation and receiving the echces. The echo received from the front surface of the specimen is balanced out by means of a bridge circuit. The echo from the clad core interface contains formation concerning the thickness of the clad. The echo has a positive peak followed by a small negative peak. The ''crossing point'' between the positive and negative peak or the amplitude of the echo can be used to determine clad thickness. One of the difficult problems with this technique is the extreme sensitivity to variations in probe-to-metal spacing. Methods for eliminating or minimizing this effect have been tried, with some success. (auth)
Date: May 1, 1955
Creator: Waidelich, D.L.; DeShong, J.A. & McGonnagle, W.J.
System: The UNT Digital Library
Purex Pulse Generator Operation (open access)

Purex Pulse Generator Operation

None
Date: May 11, 1955
Creator: McCarthy, P. B.
System: The UNT Digital Library
RATIO OF U-232 TO U-233 PRODUCED IN THE TBR (open access)

RATIO OF U-232 TO U-233 PRODUCED IN THE TBR

The production of U/sup 232/ in the cost optimized TBR and oneregion thorlum oxide-uranium oxide slurry reactor has been estimated to be, respectively, 40 and 260 parts per million parts of U/sup 233/ produced. These production rates are compared with corresponding production rates in irradiated thorium rods and found to be comparable. Recommendations are made for increasing the purity of the U/sup 233/ product. (auth)
Date: May 23, 1955
Creator: Dresner, L
System: The UNT Digital Library
Reactor Section, radiation monitoring report for month of April 1955 (open access)

Reactor Section, radiation monitoring report for month of April 1955

This document details radiation monitoring activities of the Reactor Section during the month of April 1955.
Date: May 4, 1955
Creator: Jerman, P. C.
System: The UNT Digital Library
The Relationship of Thermally Induced Hemoglobinemia to Volume of Skin Burn (open access)

The Relationship of Thermally Induced Hemoglobinemia to Volume of Skin Burn

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Date: May 27, 1955
Creator: Lyon, J. L.; Emery Jr., A. J.; Pearse, H. E. & Davis, T. P.
System: The UNT Digital Library
RESEARCH AND DEVELOPMENT IN THE FIELD OF THORIUM CHEMISTRY AND METALLURGY. Monthly Progress Report for April 16 to May 15, 1955 (open access)

RESEARCH AND DEVELOPMENT IN THE FIELD OF THORIUM CHEMISTRY AND METALLURGY. Monthly Progress Report for April 16 to May 15, 1955

A continuous belt drier capable of handling 1000 lbs of oxycarbonate per day was completed, installed, and operated to produce a satisfactory product for chlorination. An experimental chlorinator was also completed. All necessary pants were completed for the fabrication of Horizons' Mark VI continuous electrolytic cell. Evaluations of oxycarbonate materials for chlorination wiih varying chlorinating agents were made, and many of the variables such as water content and CO/sub 2/ values were established. Extremely ductile rods were obtained from the direct extrusion of Th metal powder. Plans were completed for the Mark VI electrolytic cell. Work was continued toward the development of a semi-continuous operating electrolytic cell of 7500-a rated capacity. (D.E.B.)
Date: May 25, 1955
Creator: Wyatt, J.L.
System: The UNT Digital Library
A ROTATING STEP SECTOR FOR USE WITH AC OR OTHER INTERMITTENT SPECTROGRAPHIC LIGHT SOURCES (open access)

A ROTATING STEP SECTOR FOR USE WITH AC OR OTHER INTERMITTENT SPECTROGRAPHIC LIGHT SOURCES

None
Date: May 1, 1955
Creator: Kniseley, R.N. & Fassell, V.A.
System: The UNT Digital Library
Safety Experience: Reactor and Critical Facilities (open access)

Safety Experience: Reactor and Critical Facilities

This document provides a discussion of reactor safety of the Hanford production reactor and critical facilities. A description of each facility is provided and details of significant safety incidents are provided.
Date: May 6, 1955
Creator: Greager, O. H.
System: The UNT Digital Library
The Separation of Uranium and Plutonium Isotopes in Chemical Exchange Systems (open access)

The Separation of Uranium and Plutonium Isotopes in Chemical Exchange Systems

The theory and results of chemical exchange experiments for separation of Pu and U isotopes are presented. Solvent extraction systems were studied in both aqueous and organic media. Chemical exchange systems are proposed which could yield high separation factors. (W.L.H.)
Date: May 16, 1955
Creator: Hahn, H.T.
System: The UNT Digital Library
A SIMPLIFIED SAFETY ROD ACTUATOR (open access)

A SIMPLIFIED SAFETY ROD ACTUATOR

None
Date: May 1, 1955
Creator: Baker, D. Jr.; Llewellyn, W.E. & Maloney, J.P.
System: The UNT Digital Library