Resource Type

Survey of Nonmetallic Liquid Coolants for Nuclear-Power Piles (open access)

Survey of Nonmetallic Liquid Coolants for Nuclear-Power Piles

A comprehensive survey of the literature was made in an effort to identify nonmetallic materials of possible usefulness as liquid coolants. Materials having maximum melting points of 1000 deg F and boiling points of l200 deg F were considered, but boiling points above 2200 deg F were preferred. Melting points, boiling points, densities, heat capacities, and thermal conductivities were tabulated. Approximately 190 materials appeared to have melting and boiling temperatures in a suitable range. A paucity of thermal- conductivty and heat-capacity data prevented further estimates of suitability of all but nine of these materials. Of these nine nonmetallics, only sodium hydroxide appeared to offer possibilities when considered according to the NEPA formula. (M.C.G.)
Date: May 26, 1950
Creator: Shaw, H.L. & Boulger, F.W.
System: The UNT Digital Library
High Energy Excitation Functions in the Heavy Region (open access)

High Energy Excitation Functions in the Heavy Region

The electrostatically deflected beam of the 184-inch cyclotron has been used with the stacked foil and absorber technique to determine the excitation functions for the following reactions: Th{sup 232}(p,6n)Pa{sup 227}, Th{sup 232}(p,3n)Pa{sup 230}, Th{sup 232}(d,7n)Pa{sup 227}, Th{sup 232}({alpha},p8n)Pa{sup 227}, Th{sup 232}({alpha},p5n)Pa{sup 230}, and U{sup 238}(p,{alpha}8n)Pa{sup 227}. The data are presented graphically and discussed individually for each of the reactions. Some rough excitation function data have also been determined for the reactions Th{sup 232}(d,4n)Pa{sup 230}, U{sup 238}(p,{alpha}5n)Pa{sup 230}, Th{sup 232}({alpha},7n)U{sup 229}, and Th{sup 232}({alpha},6n)U{sup 230}. The results are discussed in terms of compound nucleus formation, transparency effects, and other factors in order to arrive at a qualitative picture for the mechanism of high energy nuclear reactions with heavy nuclei.
Date: September 26, 1950
Creator: Meinke, W. W.; Wick, G. C. & Seaborg, G. T.
System: The UNT Digital Library
The New Element Berkelium (Atomic Number 97) (open access)

The New Element Berkelium (Atomic Number 97)

An isotope of the element with atomic number 97 has been discovered as a product of the helium-ion bombardment of americium. This isotope decays with the emission of alpha-particles of maximum energy 6.72 Mev (30 percent) and it emits lower energy alpha-particles of energies 6.55 Mev (53 percent) and 6.20 Mev (17 percent). The half-life of this isotope is 4.6 hours and it decays primarily by electron capture with about 0.1 percent branching decay by alpha-particle emission. The mass number is probably 243 as indicated by chemical separation of the alpha-particle and electron-capture daughters. The name berkelium, symbol Bk, is proposed for element 97. The chemical separation of element 97 from the target material and other reaction products was made by combinations of precipitation and ion exchange adsorption methods making use of its anticipated (III) and (IV) oxidation states and its position as a member of the actinide transition series. The distinctive chemical properties made use of in its separation and the equally distinctive decay properties of the particular isotope constitute the principal evidence for the new element.
Date: April 26, 1950
Creator: Thompson, S. G.; Ghiorso, A. & Seaborg, G. T.
System: The UNT Digital Library
Preliminary Studies of Scavenging Systems Related to Radioactive Fallout : Ninth Letter Report, August 1 to October 1, 1959 (open access)

Preliminary Studies of Scavenging Systems Related to Radioactive Fallout : Ninth Letter Report, August 1 to October 1, 1959

Introduction: "This is the ninth letter report on ARF Project C 127, entitled "Preliminary Studies of Scavenging Systems Related to Radioactive Fallout." This report covers the period from August 1 to October 1, 1959."
Date: October 26, 1959
Creator: Stockham, John D. & Rosinski, John
System: The UNT Digital Library
A Study of Thorium-Base Alloys (open access)

A Study of Thorium-Base Alloys

Report discussing studies testing various thorium alloys consisting of either Ames thorium and up to 5% of various additions or Ames thorium and up to 50% uranium. Effects of molybdenum additions for fusion welding, and cold-work strengthening were also tested. Methods, experimental data, and discussion is included.
Date: December 26, 1951
Creator: Goldhoff, R. M.; Ogden, Horace R. & Jaffee, Robert Isaac, 1917-
System: The UNT Digital Library
Hydroxides as Moderator Coolants in Power-Breeder-Reactors (open access)

Hydroxides as Moderator Coolants in Power-Breeder-Reactors

The following report describes work that was udertaken to determine whether a homogeneous breeder reactor using an alkili metal hydroxide solution is capable of breeding.
Date: March 26, 1952
Creator: Dayton, Russell Wendt & Chastain, Joel W.
System: The UNT Digital Library
Plastic Flow During Extrusion of Tubing (open access)

Plastic Flow During Extrusion of Tubing

Abstract: "A study of plastic flow during the extrusion of tubing was made by extruding colored Plasticine billets in a small-scale extrusion press. Decreasing the included angle of the conical die and tapering the ram end of the billet decreased the amount of coextrusion of the backer block into the tubing, lubricating the billet also decreased coextrusion."
Date: July 26, 1955
Creator: Saller, Henry A.; Keeler, John R. & Cuddy, Lee J.
System: The UNT Digital Library
Dissolution of Aluminum-Canned Thorium (open access)

Dissolution of Aluminum-Canned Thorium

The following report studies the dissolution of aluminum-canned thorium, providing results that suggest a dissolution cycle that permits the separation of the canned-slug components.
Date: July 26, 1955
Creator: Beach, John G.; Schickner, William C. & Faust, Charles L.
System: The UNT Digital Library
Theoretical Analysis of the Interference Effects of Several Supersonic Tunnel Walls Capable of Absorbing the Shock Caused by the Nose of a Model (open access)

Theoretical Analysis of the Interference Effects of Several Supersonic Tunnel Walls Capable of Absorbing the Shock Caused by the Nose of a Model

Memorandum presenting a theoretical analysis of the supersonic flow about two-dimensional and three-dimensional axially symmetric models restricted by theoretical walls capable of removing the nose shock. Results regarding the supersonic-tunnel interference due to nonreflecting walls and supersonic-tunnel interference due to porous walls are provided.
Date: May 26, 1958
Creator: Matthews, Clarence W.
System: The UNT Digital Library
Hydrogen for Turbojet and Ramjet Powered Flight (open access)

Hydrogen for Turbojet and Ramjet Powered Flight

Memorandum presenting various reports regarding the use of hydrogen for turbojet and ramjet powered flight. Some of the characteristics considered include the combustion properties, potential fueling problems, and flight experience with hydrogen on-board.
Date: April 26, 1957
Creator: Lewis Flight Propulsion Laboratory
System: The UNT Digital Library
Nickel ferricyanide scavenging flowsheet for neutralized concentrated raw (open access)

Nickel ferricyanide scavenging flowsheet for neutralized concentrated raw

From the startup of the TBP Plant until late in September, 1954, when in-line scavenging operations were begun, the wastes from the TBP Plant had been stored after neutralization and concentration in underground storage tanks. Some of this TBP waste has been given a secondary concentration in the waste concentration facilities (first cycle waste evaporators) at the tank farms. Studies by the chemistry Unit have indicated that a further reduction in the volume of waste permanently stored is possible by scavenging these wastes. In this document, a chemical flowsheet is presented for use as a design basis of facilities which will permit scavenging of these stored wastes.
Date: October 26, 1954
Creator: Smith, R. E. & Coppinger, E. A.
System: The UNT Digital Library
Stability Constants of Alphahydroxyisobutyric Acid Complexes With Actinide Elements (open access)

Stability Constants of Alphahydroxyisobutyric Acid Complexes With Actinide Elements

From abstract: "The stability constants of curium and americium alpha hydroxyisobutyrate complexes were determined by means of ion exchange equilibrium measurements on Dowex-50 four percent resin in the ammonium form."
Date: September 26, 1956
Creator: Odenheimer, B. Graus & Choppin, Gregory R.
System: The UNT Digital Library
Note on Table Top Injection : High Energy Injection Inside the Mirrors (open access)

Note on Table Top Injection : High Energy Injection Inside the Mirrors

"High energy injection into Table Top is discussed for the case in which the ion sources are to be located inside the mirrors in the mirror region. Two typical ion source geometries are considered. maximum time intervals available for injection indicated are on the order of 7 to 25 microseconds."
Date: August 26, 1955
Creator: Hiskes, J. R.
System: The UNT Digital Library
Production of a High Energy Neutral H or D Beam (open access)

Production of a High Energy Neutral H or D Beam

This report discusses methods of high energy plasma. It elaborates on these methods and their use of high energy particles.
Date: January 26, 1956
Creator: Gibson, Gordon & Lauer, E. J.
System: The UNT Digital Library
Water treatment modifications to present areas (open access)

Water treatment modifications to present areas

It is the purpose of this document to review and up-date the previously presented scope basis for the activated silica installations in light of the existence of the Phase I portion and the present expected water flow requirements of Project CG-558. It is the further purpose to outline the recommended scope bases for the sulfuric acid addition system for pH correction at all areas.
Date: January 26, 1955
Creator: Pearl, W. L.
System: The UNT Digital Library
Technical basis for establishing process tube pressure limits for KER loops 2 and 3 and for the NPR Prototype Facility (open access)

Technical basis for establishing process tube pressure limits for KER loops 2 and 3 and for the NPR Prototype Facility

In compliance with a request from Coolant Testing Operation, the Reactor Engineering Operation has made a study to determine the maximum operating pressure limits for the pertinent Zircaloy-2 process tubes. Since these tubes shall be used for testing NPR fuel elements, it is considered desirable that KER Loops 2 and 3 permit operation at temperatures of around 300{degrees}C while the NPR prototype facility permit operation at about 316{degrees}C in a manner such that there is minimum hazard to the KE-Reactor and to personnel.
Date: June 26, 1959
Creator: Adams, O. E.
System: The UNT Digital Library
Acenaphthene solvents for use in Building 313 Frost Test operation (open access)

Acenaphthene solvents for use in Building 313 Frost Test operation

Acenaphtheno is a low-melting organic compound, C{sub 10}H{sub 6}(CH{sub 2}){sub 2}, used as a temperature indicating coating for slugs tested in the Frost Test induction coil. In preparation for this test, slugs are coated by spraying a 12 to 24 per cent by weight solution of acenaphthene in a high vapor pressure solvent on the rotating slug. The solvent evaporate leaving a thin, adherent coating of acenaphthene. This process is completely described in reference 1. To be entirely satisfactory for this use, a solvent must satisfy four requirements. High vapor pressure -- rapid evaporation. Non-flammability. Low toxicity. Carbon tetrachloride, the solvent used at percent, is operationally satisfactory but undersirable because of its toxicity. The purpose of this test is to investigate the suitability of various solvents as substituted for carbon tetrachloride.
Date: June 26, 1951
Creator: Kratzer, W. K.
System: The UNT Digital Library
Hanford Atomic Products Operation monthly report, July 1955 (open access)

Hanford Atomic Products Operation monthly report, July 1955

This document presents a summary of work and progress at the Hanford Engineer Works for July 1955. The report is divided into sections by department. A plant wide general summary is included at the beginning of the report, after which the departmental summaries begin. The Manufacturing Department reports plant statistics, and summaries for the Metal Preparation, Reactor and Separation sections. The Engineering Department`s section summarizes work for the Technical, Design, and Project sections. Costs for the various departments are presented in the Financial Department`s summary. The Medical, Radiological Sciences, Utilities and General Services, Employee and Public Relations, and Community Real Estate and services departments have sections presenting their monthly statistics, work, progress, and summaries.
Date: August 26, 1955
Creator: unknown
System: The UNT Digital Library
Monthly report of the Design Analysis Group for September 1954 (open access)

Monthly report of the Design Analysis Group for September 1954

The following topics were discussed in this report: pressurization of the rear face for existing reactors; loss of steam in existing reactors; in-pile boiling in the 105-KER recirculation facilities; feasibility report for special study reactor plant; shielding requirements of the special study reactor plant; sulfuric acid addition to 100-K; radiation from activated iron in a recirculating system; ion exchanger activity from Fe corrosion; thermal shock-KER loop; shielding of tube bundles; adjustment of raw water pH; and Zircaloy fuel element jackets.
Date: October 26, 1954
Creator: Andersen, R. K.
System: The UNT Digital Library
Production test IP-245-A dual area trip-out of B & C Reactor process pumps (open access)

Production test IP-245-A dual area trip-out of B & C Reactor process pumps

The objectives of the test described in this report are to obtain current knowledge of the flow characteristics of the B and C Reactor flow systems under various transient conditions that have a reasonable probability of occurrence. These tests will be used to revaluate the B and C Reactor bulk temperature limits, the Ball 3X low pressure trip settings, and quantitative adequacy of emergency flow from the combined high tanks - export system.
Date: March 26, 1959
Creator: Long, J. T. & Jones, S. S.
System: The UNT Digital Library
Vacuum nitric acid fractionation in the Purex Plant (open access)

Vacuum nitric acid fractionation in the Purex Plant

None
Date: January 26, 1954
Creator: Sloat, R. J. & Smith, R. E.
System: The UNT Digital Library
RADIATION HAZARDS FROM THE USE OP DENTAL X-RAY UNITS (open access)

RADIATION HAZARDS FROM THE USE OP DENTAL X-RAY UNITS

It is well known that for many years x-rays have been used in the dental profession as a potent diagnostic tool. Deprived of this means of exploration, the dentist and patient alike would be at a great disadvantage. In spite of the necessity of x-rays in the dental field, little has been done, however, to protect the patient and the dentist from unnecessary exposure. X-rays cannot immediately be felt or seen, and therein lies the hazard attending their use. What cannot be sensed is often ignored, and through unconcern and neglect an exposure resulting in biological impairment or damage may result. It was felt therefore, that the potential hazard occurring during oral roentgenography should be investigated and that the results of the investigation would be of interest to the dental profession. Radiation survey results are shown for six dentists' offices in the San Francisco Bay area.
Date: November 26, 1952
Creator: Nolan, W. E. & Patterson, H. W.
System: The UNT Digital Library
K Reactor natural I&E goal exposure (open access)

K Reactor natural I&E goal exposure

Return can be increased on the order of $1000 to $2000 per calendar day at each K Reactor if the goal exposure for natural I & E slugs is reduced from 800 to 700 MWD/T. This gain is predicated on primarily a decrease in rupture losses. The recommended goal is a straight line on a linear graph of exposure in MWD/T versus maximum tube power in kw per tube, passing through the following two points: (850 kw/tube, 900 MWD/T); (1400 kw/tube; 490 MWD/T). In addition, I & E natural uranium charges running below 850 kw, if any, should be discharged not higher than 900 MWD/T. At a maximum tube power of 1300 kw, the recommended goal will give a weighted average exposure of about 700 MWD/T. Power at which a tube operates should be determined as recommended in HW-57937, ``Goal Exposure for Enriched I & E Material at the C and K Reactors.`` These are interim recommendations. We expect to recommend some changes in the goal, for reasons explained below. The recommended goal was calculated on the IBM-650, using an equation for return. The equation included, we believe, proper allowance for all but two factors. Principle affecting factors were included.
Date: November 26, 1958
Creator: Music, J. F.
System: The UNT Digital Library
Hanford Atomic Products Operation monthly report, June 1954 (open access)

Hanford Atomic Products Operation monthly report, June 1954

This document presents a summary of work and progress at the Hanford Engineer Works for June 1954. The report is divided into sections by department. A plant wide general summary is included at the beginning of the report, after which the departmental summaries begin. The Manufacturing Department reports plant statistics, and summaries for the Metal Preparation, Reactor and Separation sections. The Engineering Department`s section summaries work for the Technical, Design, and Project Sections. Costs for the various departments are presented in the Financial Department`s summary. The Medical, Radiological Sciences, Utilities and General Services, Employee and Public Relations, and Community Real Estate and Services departments have sections presenting their monthly statistics, work, progress, and summaries.
Date: July 26, 1954
Creator: unknown
System: The UNT Digital Library