Natural convection reactor (open access)

Natural convection reactor

A previous report described the conceptual design of a plutonium producing reactor that may be characterized as follows: Power output (2000 MW); cooling - (natural convection of light water through the reactor, up through a draft tube to an evaporative cooling pond, then back to the reactor, and fuel (400 to 500 tons of uranium enriched to 1.2% U-235). Because this reactor would be cooled by the natural convection of light water, it is believed that the construction costs would be significantly less than for a Savannah or Hanford type reactor. Such expensive items as water treatment and water pumping facilities would be eliminated entirely. The inventory of 500 tons of slightly enriched uranium, however, is an unattractive feature. It represents not only a large dollar investment but also makes the reactor less attractive for construction during periods of national emergency because of the almost certain scarcity of even slightly enriched uranium at that time. The Atomic Energy Commission asked that the design be reviewed with the objective of reducing the inventory of uranium, The results of this review are given in this report.
Date: May 1, 1956
Creator: Babcock, D. F.; Bernath, L.; Menegus, R. L. & Ring, H. F.
Object Type: Report
System: The UNT Digital Library
A Pilot Plant for the Reduction of Uranium Hexafluoride to Uranium Tetrafluoride with Trichloroethylene (open access)

A Pilot Plant for the Reduction of Uranium Hexafluoride to Uranium Tetrafluoride with Trichloroethylene

Pilot plant experiments are described in which trichloroethylene was used for the reduction of uranium hexafluoride to uranium tetrafluoride. After unsatisfactory preliminary results with liquid phase reduction, satisfactory results were obtained with a vapor phase reduction system. It was found that vapor phase reduction at approximately 450 deg F, produced a low density product which contained only small quantities of uranium(VI); sintering the uranium tetrafluoride in a hydrogen fluoride atmosphere increased the product density to approximately 3 g/cc. The reduction was essentially complete, and the effluent gas contained less than 1 ppm of uranium hexafluoride. The purity of the uranium tetrafluoride produced was equivalent to that of the uranium hexafluoride used as feed. A complete discussion is given of the operation of the various parts of the system. (auth)
Date: May 31, 1956
Creator: Baker, J. E.; Klaus, H. V.; Schmidt, R. A. & Smiley, S. H.
Object Type: Report
System: The UNT Digital Library
A Comparison of the Effects of Radiant Thermal Energy on Bare, Blackened and Whitened Pig Skin (open access)

A Comparison of the Effects of Radiant Thermal Energy on Bare, Blackened and Whitened Pig Skin

None
Date: May 24, 1956
Creator: Bales, H. W.; Hinshaw, J. R. & Pearse, H. E.
Object Type: Report
System: The UNT Digital Library
Sites of Azaserine Inhibition During Photosynthesis byScenedesmus (open access)

Sites of Azaserine Inhibition During Photosynthesis byScenedesmus

The success attending the use of azaserine as a specific inhibitor of one atage in the metabolic pathway leading to the synthesis of inosinic acid in pigeon liver prompted us to use this antibiotic in a similar attack on purine synthesis in Scenedesmus. However, investigation of the products produced during photosynthesis by suspensions of these algae in the presence of azaserine showed that a more widespread interference with metabolism had occurred. The purpose of this communication is to describe the nature of these effects and to attempt to assess their importance in a general picture of the metabolic effects of azaserine.
Date: May 8, 1956
Creator: Barker, S. Alan; Bassham, James A.; Calvin, M. & Quarck, Ursula C.
Object Type: Report
System: The UNT Digital Library
Flow test: CG-482 ``DR type`` rear pigtail with B, D, DR and F pile fittings (open access)

Flow test: CG-482 ``DR type`` rear pigtail with B, D, DR and F pile fittings

This letter transmits the data from the 189-D Hydraulics Laboratory flow test on three CG-482 rear pigtails. The tests were run with a standard B, D, Dr and F rear nozzle and rear Parker fitting over the range of flows and temperatures anticipated for early CG-558 operation. The data from the test are given. All three pigtails gave essentially identical results. For comparison the results of previous tests with present rear pigtails are also plotted.
Date: May 25, 1956
Creator: Bell, K. J.
Object Type: Report
System: The UNT Digital Library
Mixing in a river (open access)

Mixing in a river

Many rivers are burdened with tributary streams of warm water and/or liquid wastes containing dissolved or suspended matter. The warm water and waste matter mix thoroughly with the river water some distance downstream from the point of entry of the tributary, but near the point of entry there may be high local temperatures or concentrations of waste. It is often necessary to know the local temperatures or concentrations of waste. The authors have used a formula for computing the turbulent mixing that takes place in such a situation; this formula fits quite well in the case of one Southern river.
Date: May 9, 1956
Creator: Bernath, L.; Menegus, R. L. & Ring, H. F.
Object Type: Report
System: The UNT Digital Library
Chemical Development Status Report for Week Ending May 11, 1956 (open access)

Chemical Development Status Report for Week Ending May 11, 1956

None
Date: May 15, 1956
Creator: Blanco, R. E. & Ferguson, D. E.
Object Type: Report
System: The UNT Digital Library
Chemical Development Status Report for Week Ending May 18, 1956 (open access)

Chemical Development Status Report for Week Ending May 18, 1956

None
Date: May 23, 1956
Creator: Blanco, R. E. & Ferguson, D. E.
Object Type: Report
System: The UNT Digital Library
POWER REACTOR FUEL PROCESSING PRELIMINARY REPORT (open access)

POWER REACTOR FUEL PROCESSING PRELIMINARY REPORT

None
Date: May 14, 1956
Creator: Blanco, R. E.; Eister, W. K. & Ferguson, D. E.
Object Type: Report
System: The UNT Digital Library
SOME PROBLEMS IN THE SAFETY OF FAST REACTORS (open access)

SOME PROBLEMS IN THE SAFETY OF FAST REACTORS

None
Date: May 1, 1956
Creator: Brittan, R.O.
Object Type: Report
System: The UNT Digital Library
Electric Conduction in an Oil-Pumped Vacuum System (open access)

Electric Conduction in an Oil-Pumped Vacuum System

The leakage of electricity aoross a vacuum space in an electrostatic generator which employs a mixture of Sr/sup 90/ and Y/sup 90/ as the source of charging current was investigated. The vacuum is obtained by means of an oil pump. The leakage was shown to consist of a flow of positive and negative particles between the anode and the cathode. The positive particles were found to be primarily organic ions produced in a layer of oil on the surface of the anode. The negative particles were shown to be mostly electrons. Yields of secondary negative particles and secondary positive particles produced by average positive particles in the energy range from 50 to 200 kev were measured. Yields were found to be dependent on the nature of the target material as well as on the energy of the incident ion. A mass spectrometer was employed to study the nature of the positive ions. Most of these were charged fragments of organic molecules. Neutral particles were attributed to dissociation of a portion of positive ions during their flight from the anode to cathode. Electrons, most of which originate at the beta source, are presumed to be the agent for positive ion production. …
Date: May 1, 1956
Creator: Bryant, Ernest A.
Object Type: Thesis or Dissertation
System: The UNT Digital Library
Final report -- PT-105-548-A, The effect of masonite burnout on shield attenuation properties (open access)

Final report -- PT-105-548-A, The effect of masonite burnout on shield attenuation properties

In a previous study it was determined experimentally that heat deterioration, or burnout, of the shield masonite is more severe than radiation damage under existing and proposed operating conditions. Higher shield temperatures, which are expected to result from increased power levels, fringe enrichment, and higher graphite temperatures, will markedly increase the rate at which the masonite burns out. The laminated iron-masonite biological shield will lose, as a result of burnout, the hydrogen and oxygen necessary to attenuate and moderate neutrons. The purpose of this production test has been to obtain experimental data from which future shield leakage rates could be estimated. The attenuation data reported here were obtained in the DR pile bulk shield facility from experiments using various void spacings to simulate burnout conditions. From these data it was hoped to determine (1) the resultant attenuation properties of the shields, and (2) the exposure rates due to radiation penetrating the shield.
Date: May 23, 1956
Creator: Bunch, W. L.
Object Type: Report
System: The UNT Digital Library
Thermochemical Measurements of Purex Process Solutions (open access)

Thermochemical Measurements of Purex Process Solutions

None
Date: May 1956
Creator: Burney, G. A.
Object Type: Report
System: The UNT Digital Library
Cryogenic Data Book (open access)

Cryogenic Data Book

Increased activities in Cryogenic Engineering have brought about the need for a compilation of available data. The purpose of the Cryogenic Data Book is to provide a condensed source of reliable data and reference information for those working in the cryogenic field. Specifically the data were compiled with a view toward the design of liquid hydrogen bubble chambers.
Date: May 15, 1956
Creator: Chelton, Dudley B.; Mann, Douglas B.; Byrns, R. A. & Hoard, H. S.
Object Type: Report
System: The UNT Digital Library
Tabulation of radioactive liquid waste disposal facilities (open access)

Tabulation of radioactive liquid waste disposal facilities

The following lists describe facilities in the Hanford project for disposal of radioactive liquid waste into the ground. Most are for planned disposals, but included are several which were not intended to become contaminated, but did, and several others which may be expected to become contaminated similarly. Not included are sanitary, powerhouse and a few other liquid disposal facilities which may receive only insignificant amounts of radioactive material. The lists do not include solid waste disposal facilities, or others (such as tanks, buried barrels) in which contaminated liquid is contained against entry into the soil.
Date: May 10, 1956
Creator: Clukey, H. V.
Object Type: Report
System: The UNT Digital Library
PUMP FAILURE AND THE APPR-1 (open access)

PUMP FAILURE AND THE APPR-1

None
Date: May 1, 1956
Creator: Coneybear, J. Frank; Berggren, Willard P.; Culp, Archie W., Jr.; Grisak, Fred R. & Kroeger, Henry R.
Object Type: Report
System: The UNT Digital Library
Summary Hazards Report on Enriched Fuel Element Loading for the BNL Research Reactor (open access)

Summary Hazards Report on Enriched Fuel Element Loading for the BNL Research Reactor

None
Date: May 24, 1956
Creator: Corngold, N.
Object Type: Report
System: The UNT Digital Library
PLUTONIUM HAZARDS CREATED BY ACCIDENTAL OR EXPERIMENTAL DETONATION OF ATOMIC WEAPONS (open access)

PLUTONIUM HAZARDS CREATED BY ACCIDENTAL OR EXPERIMENTAL DETONATION OF ATOMIC WEAPONS

None
Date: May 1, 1956
Creator: Corsbie, R.L.
Object Type: Report
System: The UNT Digital Library
Preliminary Draft - Economics of Waste Disposal (open access)

Preliminary Draft - Economics of Waste Disposal

None
Date: May 29, 1956
Creator: Culler, Jr., Floyd L.
Object Type: Report
System: The UNT Digital Library
Progress Relating to Civilian Applications During April 1956 (open access)

Progress Relating to Civilian Applications During April 1956

None
Date: May 1, 1956
Creator: Dayton, R. W. & Tipton, C. R., Jr.
Object Type: Report
System: The UNT Digital Library
Procedure for Testing Holdup Tank HRT Test No. II A-22 a, b (open access)

Procedure for Testing Holdup Tank HRT Test No. II A-22 a, b

None
Date: May 28, 1956
Creator: Engel, J. R. & Haubenreich, P. N.
Object Type: Report
System: The UNT Digital Library
Ibm Sub-Routines. [Part] 2. Irregular Bessel Functions (open access)

Ibm Sub-Routines. [Part] 2. Irregular Bessel Functions

None
Date: May 1956
Creator: English, J. C.
Object Type: Report
System: The UNT Digital Library
Metallurgy Division SemiAnnual Progress Report for Period Ending October 10, 1955 (open access)

Metallurgy Division SemiAnnual Progress Report for Period Ending October 10, 1955

Static corrosion tests in sodium and in fused-fluoride-salt mixture on type 310 stainless steel T-joints brazed with various alloys by the Wall Colmonoy Corporation indicate that the 9% Si-2.5% P-88.5% Ni alloy has fair resistance to both media.
Date: May 11, 1956
Creator: Frye, J. H.; Manly, W. D. & Cunningham, J. E.
Object Type: Report
System: The UNT Digital Library
HOT CHANNEL FACTORS AND POWER DISTRIBUTIONS FOR THE APPR-1 (open access)

HOT CHANNEL FACTORS AND POWER DISTRIBUTIONS FOR THE APPR-1

None
Date: May 1, 1956
Creator: Gallagher, J.G.
Object Type: Report
System: The UNT Digital Library