A Pebble-Bed Reactor for Stationary Power Plants (open access)

A Pebble-Bed Reactor for Stationary Power Plants

None
Date: May 15, 1954
Creator: Beeley, R. J.
System: The UNT Digital Library
Production Test No. 105-565-A: Horizontal rod conversion---old piles (open access)

Production Test No. 105-565-A: Horizontal rod conversion---old piles

In numerous instances the graphite growth in the older piles has deformed the horizontal control rod holes with a resultant jamming of the rods and overstressing of the rods and thimbles. In addition, special operating procedures to maintain very low differential pressures are required with the present allowed maximum graphite temperatures to prevent collapse of the thimbles because of loss of strength at this temperature. This is currently a limit to the power level of the H Pile. This report discusses a new rod tip and seal which have been developed to allow the removal of the thimble and permit sealing at the pile face. This will allow advantage to be taken of any future increases in maximum graphite temperature with proportional increases in allowable power.
Date: February 15, 1954
Creator: Call, R. L.; Rector, J. H. & Lovington, R. C.
System: The UNT Digital Library
An Introduction to the Purex Plant (open access)

An Introduction to the Purex Plant

The intent of this manual is to present a description of the main process building, equipment, and auxiliary facilities as well as a process summary. Material is of a scope nature with more detail devoted to features unlike those of existing separations systems. An attempt is made to convey some of the basic design philosophy and the problems encountered in the development of design criteria. This information is written primarily for Separations Section supervision who have not had an opportunity to become conversant with the Purex Project. The manual may also be of assistance in orientation and training of personnel. In order to avoid repetition and duplication of effort, one line service diagrams, equipment sketches, tables, and detailed data are not a part of this manual.
Date: July 15, 1954
Creator: Courtney, J. J. & Clark, B. E., Jr.
System: The UNT Digital Library
The Evaporation of Plutonium From Small Pieces of Uranium Reactor Fuel (open access)

The Evaporation of Plutonium From Small Pieces of Uranium Reactor Fuel

None
Date: October 15, 1954
Creator: Cubicciotti, D.
System: The UNT Digital Library
PURIFICATION OF NUCLEAR FUELS BY MELTING IN REFRACTORY OXIDE CRUCIBLES. Interim Report (open access)

PURIFICATION OF NUCLEAR FUELS BY MELTING IN REFRACTORY OXIDE CRUCIBLES. Interim Report

None
Date: March 15, 1954
Creator: Feder, H.M.; Chellew, N.R. & Ader, M.
System: The UNT Digital Library
Effects of Vibration-Aging on Certain Types of Receiving Tubes (open access)

Effects of Vibration-Aging on Certain Types of Receiving Tubes

None
Date: November 15, 1954
Creator: Ford, G T
System: The UNT Digital Library
FABRICATION OF ZIRCONIUM SHELLS. Part 2. A Technical Progress Report and Tentative Development Specifications (for) November 1952-June 1953 (open access)

FABRICATION OF ZIRCONIUM SHELLS. Part 2. A Technical Progress Report and Tentative Development Specifications (for) November 1952-June 1953

None
Date: March 15, 1954
Creator: French, R. S.; Mayer, C. H. & Pratt, R. S.
System: The UNT Digital Library
DEPOSITION OF SUSPENDED PARTICLES FROM TURBULENT GAS STREAMS. Technical Report No. 13 (open access)

DEPOSITION OF SUSPENDED PARTICLES FROM TURBULENT GAS STREAMS. Technical Report No. 13

None
Date: September 15, 1954
Creator: Friedlander, S.K.
System: The UNT Digital Library
A note on the behavior of stack gases (open access)

A note on the behavior of stack gases

The ability of the atmosphere to disperse and diffuse smoke and gases varies widely with weather conditions. The rate of diffusion is governed mainly by the degree of atmospheric turbulence present. The latter is in itself an extremely complex air motion which acts as the mixing agent in diffusion. This turbulence, which is so fundamental in the diffusion process, depends on such quantities as wind speed, rate of change of wind speed or wind direction with height, and rate of change of air temperature with height. Since these conditions differ widely from hour to hour and day to day, there is a corresponding variation in the diffusing capacity of the atmosphere. The rate of change of temperature with height and the wind speed have the most pronounced effect on the physical appearance of smoke plumes, which in itself provides a clue to the diffusing power of the atmosphere during various atmospheric conditions. The purpose of this note is to present, in semi-technical terms, some of the basic physical concepts related to the behavior of gaseous stack effluents after release into the atmosphere, and to describe certain visible geometrical features of effluent plumes that are directly related to the physical state …
Date: December 15, 1954
Creator: Fuquay, J. J. & Shorr, B.
System: The UNT Digital Library
DEFORMATION MECHANISM IN POLYCRYSTALLINE AGGREGATES OF MAGNESIUM. TECHNICAL REPORT NO. 1 FOR JUNE 1, 1953 TO MARCH 1, 1954 (open access)

DEFORMATION MECHANISM IN POLYCRYSTALLINE AGGREGATES OF MAGNESIUM. TECHNICAL REPORT NO. 1 FOR JUNE 1, 1953 TO MARCH 1, 1954

None
Date: March 15, 1954
Creator: Hauser, F.E.; Starr, C.D.; Tietz, L.S. & Dorn, J.E.
System: The UNT Digital Library
Determination of Sr{sup 90}, Sb{sup 125}, Cs{sup 137} and absolute beta activities in First Cycle Supernatent (open access)

Determination of Sr{sup 90}, Sb{sup 125}, Cs{sup 137} and absolute beta activities in First Cycle Supernatent

This report discusses procedures have been established for determining the absolute activities of Sr{sup 90}, Sb{sup 125}, Cs{sup 137}, and gross beta in First Cycle Supernatant. These procedures are also valid for other samples such as scavenged Radioactive Waste (RAW), the primary restriction being that the age of the material be at least 250 days so that any Sr{sup 89} activity (53 day half-life) is negligible. With the exception of the gross beta analysis the results are believed to be accurate to within 10%.
Date: March 15, 1954
Creator: Helmholz, H. R.
System: The UNT Digital Library
Disposal of 100-C effluent through ground percolation (open access)

Disposal of 100-C effluent through ground percolation

None
Date: March 15, 1954
Creator: Honstead, J. F.
System: The UNT Digital Library
Migration Areas of Fission Neutrons in Uranium-Water Lattices (open access)

Migration Areas of Fission Neutrons in Uranium-Water Lattices

None
Date: December 15, 1954
Creator: Kouts, H.; Price, G.; Downes, K.; Sher, R. & Walsh, V.
System: The UNT Digital Library
Summary of data on boiling flow from the 189-D tube mock-ups (open access)

Summary of data on boiling flow from the 189-D tube mock-ups

During 1954 interest was maintained in the problem of cooling-by-boiling in a geometry similar to that of a Hanford pile. Operation of present piles and the design of future piles will benefit from basic knowledge of boiling flow. This report presents a brief compilation of data for boiling flow taken during the year on the full scale and short process tube mock-ups in 189-D. Data reported herein consists of burnout conditions for a uniform heat flux in a `C` annulus and a standard annulus and data taken with full cosine and part cosine power distribution. The data for non-uniform power distribution is meager and was taken primarily to obtain an indication of the validity of extrapolating data with uniform heat flux to conditions of non-uniform flux distribution.
Date: December 15, 1954
Creator: McNutt, C. R.
System: The UNT Digital Library
THE FORMING OF ZIRCONIUM BY IMPACT EXTRUSION (open access)

THE FORMING OF ZIRCONIUM BY IMPACT EXTRUSION

None
Date: September 15, 1954
Creator: Rauch, W.G.
System: The UNT Digital Library
The Absorption of Neutrons in Doppler Broadened Resonances (open access)

The Absorption of Neutrons in Doppler Broadened Resonances

A method is developed for the calculation of the effect of Doppler broadening of the absorption of the neutrons by a resonance absorber. Numerical values are given for the correction factors required in the interpretation of transmission experiments and self-indication experiments and for the self-shielding factors for slabs, spheres, cylinders, and homogeneous mixtures. (auth)
Date: October 15, 1954
Creator: Roe, G. M.
System: The UNT Digital Library
Distribution of Rare-Earth Nitrates Between Tributyl Phosphate and Nitric Acid (open access)

Distribution of Rare-Earth Nitrates Between Tributyl Phosphate and Nitric Acid

None
Date: October 15, 1954
Creator: Topp, A. C. & Weaver, B.
System: The UNT Digital Library
Achievements in HAPO radiation monitoring, 1944--1954 (open access)

Achievements in HAPO radiation monitoring, 1944--1954

At HAPO the protection of employees from nuclear radiations has paralleled or preceded the emphasis on atomic products production. The production of atomic products on the scale for which HAPO was designed presented voluminous problems in employee education, radiation detection, shielding, and indeed, fundamental research to determine working limits for the various types of radiation exposure which would necessarily be encountered, and to determine working limits for the deposition of radioactive isotopes and mixtures of isotopes in the human body. Since the time radioactive materials first arrived at HAPO and the start-up of the first HAPO reactor on February 23, 1944, there has been a fundamental philosophy that all employee exposure to nuclear radiations should be maintained at a minimum, as opposed to just some level of exposure below the accepted permissible limit. It was with this philosophy in mind that the many achievements and advances in the science of radiation protection at HAPO have been forthcoming. These advances in radiation protection ar discussed in this report.
Date: September 15, 1954
Creator: Unruh, C. M.; Selby, J. M. & Sanders, F. H.
System: The UNT Digital Library
A Sodium Cooled, Graphite Moderated, Low Enrichment Uranium Reactor for the Production of Useful Power (open access)

A Sodium Cooled, Graphite Moderated, Low Enrichment Uranium Reactor for the Production of Useful Power

A design study is presented for a sodium cooled, graphite moderated power reactor utilizing low enrichment uranium fuel. The design is characterized by dependence on existing technology and the use of standard, or nearly standard, components. The reactor has a nominal rating of 167 thermal megawatts, and a plant comprising three such reactors for a total output of 500 thermal megawatts is described. Sodium in a secondary, non-radioactive, circulation system carries the heat to a steam generator at 910 deg F and is returned at 420 deg F. Steam conditions at the turbine throttle are 600 psig and 825 deg F. Cost of the complete reactor power plant, consisting of the three reactors and one 150- megawatt turbogenerator, is estimated to be approximately ,165,000. (auth)
Date: September 15, 1954
Creator: Weisner, E. F.
System: The UNT Digital Library
THEORY OF THE REACTION BETWEEN ALKALI METAL AND ALKALI HALIDES WITH APPLICATION TO THE SYSTEM K-KC1 (open access)

THEORY OF THE REACTION BETWEEN ALKALI METAL AND ALKALI HALIDES WITH APPLICATION TO THE SYSTEM K-KC1

None
Date: December 15, 1954
Creator: Westervelt, D.R.
System: The UNT Digital Library
ATTACK ON METALS BY BISMUTH-LEAD-TIN ALLOY AT ELEVATED TEMPERATURES. Final Report on Metallurgy Program 8.2.3 (open access)

ATTACK ON METALS BY BISMUTH-LEAD-TIN ALLOY AT ELEVATED TEMPERATURES. Final Report on Metallurgy Program 8.2.3

None
Date: January 15, 1954
Creator: Wilkinson, W.D.
System: The UNT Digital Library
1953 at Hanford (open access)

1953 at Hanford

The report summarizes Hanford`s operation in 1953. The 38% increase in separated plutonium over the 1952 level was one measure of achievement. 1953`s output was more than seven times that of 1947, the first full year of General Electric`s operation of Hanford. Although much of this gain resulted from new reactors, some was due to improved safety devices, and much was due to increased knowledge of the controlling factors which permitted more efficient operation of old piles and better design of new ones. Year-by-year reductions in the cost of converting uranium to plutonium tell the real story of progress at Hanford. The annual production gains could have been made by building many 1944 model piles, though at fantastic cost. Contrasted with this is the actual case--a few new, improved piles plus more production from the old ones.
Date: March 15, 1954
Creator: unknown
System: The UNT Digital Library
Reactor Engineering Division Quarterly Report for April 1, 1954 Through June 30, 1954 (open access)

Reactor Engineering Division Quarterly Report for April 1, 1954 Through June 30, 1954

None
Date: July 15, 1954
Creator: unknown
System: The UNT Digital Library
REACTOR ENGINEERING DIVISION QUARTERLY REPORT FOR PERIOD JULY 1, 1954 THROUGH SEPTEMBER 30, 1954 (open access)

REACTOR ENGINEERING DIVISION QUARTERLY REPORT FOR PERIOD JULY 1, 1954 THROUGH SEPTEMBER 30, 1954

Reactor Programs. The design of the Boiling Experimental Reactor is described. The Borax-1 reactor was intentionally destroyed by suddenly adding 4% excess reactivity. Design of the Borax-II reactor is described. It will be used for studies of transient behavior and steadystate operation as a steam producer. A preliminary design configuration has been established in EBR-II employing central, inner, and outer blankets. Fuel geometries including a smaller pin-type element are being investigated. Supporting Design, Research, and Development. The accuracy of diffusion theory for fast reactors was investigated. Water corrosion tests have been performed on high-U alloys, Zr- and Ti-base alloys, and Ni-plated Al plates. Thermal cycling tests were performed on fuel rods and pin-type fuel elements. Results are reported on tests on a current conductor connection for a high-temperature d-c electromagnetic pump, on Na valves with conventional packing, and on a rod-gripper test facility for the EBR-II. A vacuum cup sampler for high-temperature Na and NaK systems is described. Lifting and loading mechanisms for the IBR-II working model are described. (T.R.H.)
Date: October 15, 1954
Creator: unknown
System: The UNT Digital Library