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The Critical Mass of a Spherical Reactor with Variable Intrinsic Buckling (open access)

The Critical Mass of a Spherical Reactor with Variable Intrinsic Buckling

Abstract: "The critical mass both of an untamped and water-tamped sphere with parabolic radial variation of the intrinsic buckling is calculated by a perturbation method. The result is applied to finding the minimum critical mass of plutonium in water suspension with infinite water temper; the calculations show that the minimum critical mass at constant concentration may be reduced by an amount of the order of 7.6% when the concentration of plutonium is permitted to vary throughout the suspension."
Date: April 28, 1949
Creator: Muller, G. M.
System: The UNT Digital Library
Temperature distribution in the concrete shield (open access)

Temperature distribution in the concrete shield

Report describing the temperature in the Brookhaven concrete shield proposed for the X reactor. The report details the methods and equations used to find the values that determined that the effect of the gun barrel assembly in cooling the concrete is negligible.
Date: April 28, 1952
Creator: Triplett, John R.
System: The UNT Digital Library
Design Considerations for a Lattice Test Pile (open access)

Design Considerations for a Lattice Test Pile

From abstract: "The present paper proposes a lattice test pile, (or LTP) as an alternate to the continuing program of building up and tearing down of exponential piles."
Date: July 28, 1952
Creator: Horning, W. A.
System: The UNT Digital Library
The Solubility of Plutonium (IV) Monobutyl Phosphate (open access)

The Solubility of Plutonium (IV) Monobutyl Phosphate

Report discussing a study regarding the identification and property analysis of plutonium (IV) monobutyl phosphate, which formed as a white precipitate in another study of the effects of monobutyl phosphate on plutonium(IV) in tributyl phosphate extractions.
Date: June 28, 1950
Creator: Moore, Robert Lee
System: The UNT Digital Library
Examination of Masonite in Biological Shield : Interim Report (open access)

Examination of Masonite in Biological Shield : Interim Report

Introduction: "Evidence of masonite deterioration in test hole plugs was interpreted to mean that a previous estimate of the minimum lifetime of the masonite in a Hanford biological shield might be somewhat optimistic. The importance of understanding the effects of radiations on masonite for both present and future pile shields dictated that masonite be sampled from an operating pile shield and studied. The results and techniques are discussed in the following sections of this report."
Date: June 28, 1950
Creator: Dickeman, R. L.
System: The UNT Digital Library
HAPO IB Fission Product Shipping Cask Design Evaluation Report (open access)

HAPO IB Fission Product Shipping Cask Design Evaluation Report

As a result of the interest in fission products for use as heat sources and/or radiation sources, in early 1960. Hanford was authorized to supply a semi-refined cerium-144 rare earth product to Oak Ridge National Laboratories. Facilities were installed for collecting this product and a cask war designed for shipping this product as a stabilized, dry powder. Since that time, numerous improvements have been made in the design of the HAPO I cask as described in Revision O of this document. In addition, the development of strontium-90 as a major product requires increased flexibility in the utilization of these casks.
Date: December 28, 1962
Creator: Smith, C. W.
System: The UNT Digital Library
Neutron Age in Graphite-Water Lattices. (open access)

Neutron Age in Graphite-Water Lattices.

The Fermi age of thermal neutrons in a lattice containing both water and graphite in some sort of weighted average of the age in water and in graphite independently, with correction for volumes of non-moderating elements or voids. The correct weighting function has been in question during design calculations for the NPR. This paper presents a very simple and direct approach to the problem, resulting in a weighting equation which seems to be theoretically sound. Unfortunately, simple theories cannot be guaranteed to give good results in complicated systems; nevertheless, it appears that the weighting dunction derived here is to be preferred over methods involving empirical relationships which are of doubtful validity in the NPR geometry.
Date: October 28, 1959
Creator: Simpson, D. E.
System: The UNT Digital Library
Final Report:  Production Test No. 305-2-N Experimental Results Obtained From Test Pile Reactivity Measurements on Plutonium (open access)

Final Report: Production Test No. 305-2-N Experimental Results Obtained From Test Pile Reactivity Measurements on Plutonium

Measurements were taken to provide experimental evidence for determining the feasibility of a proposed method for converting Pu240 to 241 by exposing shielded plutonium to selectively transmitted pile neutrons.
Date: April 28, 1953
Creator: Lefevre, H. W & Triplett, J. R.
System: The UNT Digital Library
A Hanford Works Vacuum System (open access)

A Hanford Works Vacuum System

The remodeling, fabrication, and instrumentation of a high vacuum system are described. The faults encountered with the old system and their solution are outlined. Tests were made on diffusion pump oils and on the reduction of pump oil back diffusion. The measurement of high vacuum pressures by a cold cathode ionization gage at various points on a vacuum system are discussed.
Date: May 28, 1953
Creator: Holdreth, N. T.
System: The UNT Digital Library
Multiplication of Enriched Loading in Exponential Pile (open access)

Multiplication of Enriched Loading in Exponential Pile

This report refutes earlier calculations made in the flux level of exponential piles. The results of the earlier calculations made on subcritical assemblies using critical assembly equations are in error. The calculations used in this report were more successful.
Date: September 28, 1953
Creator: Farrand, W. B. & Lloyd, R. C.
System: The UNT Digital Library
A Study of Plutonium Trifluoride Precipitated from Aqueous Solution (open access)

A Study of Plutonium Trifluoride Precipitated from Aqueous Solution

In view of the increasing number of methods for determining plutonium in terms of weight rather than radioactivity, a need has arisen for a plutonium compound that can be used as a gravimetric standard. An easily prepared compound that dissolves readily in nitric acid is desirable. The present study was made to determine the feasibility of using plutonium triflouride as a plutonium standard. The preparation, composition, stability, and ignition of the compound are discuss, as are certain properties of the plutonium dioxide resulting from ignition of the trifluoride.
Date: December 28, 1953
Creator: Jones, M. M. (Miriam M.).
System: The UNT Digital Library
The Decontamination of Reactor Cooling Water with Aluminum (open access)

The Decontamination of Reactor Cooling Water with Aluminum

The discharge of cooling water from the Hanford reactors introduce radioactive contaminants to the Columbia River. These materials may subsequently bring about exposure to human populations either through the direct use of the water for sanitary purposes or transfers of the radioisotopes into the food chains. It is therefore desirable to keep to a minimum the amounts of radioisotopes released to the river.
Date: January 28, 1959
Creator: Silker, W. B.
System: The UNT Digital Library
A Study of the Effects of Some Spray Column Variables on Radiant-Heat Transfer in Spray Calcination (open access)

A Study of the Effects of Some Spray Column Variables on Radiant-Heat Transfer in Spray Calcination

Calcination of liquid radioactive wastes, the process of converting metal nitrates and sulfates to oxides by heat, is under development at Hanford as a means of reducing these liquids to a dry powder or solid which can be stored safely. Radiant-heat spray calcination, one of the methods under study, was first investigated at the Oak Ridge K-25 Plant (1) as a possible method of calcining uranyl nitrate to uranium trioxide. The process has also been under extensive development at the Pulp and Paper Research Institute of Canada (2) and is designated by them as the Atomized Suspension Technique.
Date: April 28, 1960
Creator: Allemann, Rudolph Theodore
System: The UNT Digital Library
Development of Pressures Tubing for the Plutonium Recycle Test Reactor (open access)

Development of Pressures Tubing for the Plutonium Recycle Test Reactor

Pressurized water nuclear reactors may be designed based upon either of two concepts: (1) pressure vessel, wherein the entire core is placed in a large, high strength fuel channels within a low pressure container. The Plutonium Recycle Test Reactor is a pressure tube type reactor. Selection of this basic type of pressurized water reactor depended to an appreciable extent upon the availability of suitable pressure tubing.
Date: April 28, 1960
Creator: Riches, J. W.
System: The UNT Digital Library
Thickness Measurement by Ultrasonic Frequency Modulation (open access)

Thickness Measurement by Ultrasonic Frequency Modulation

A prototype instrument has been designed and built which demonstrates an ultrasonic pulse echo technique of measuring metal thickness in the range .010 to .080 inches. Extension of the range of measurement on the thick side appears straightforward, however, transducer frequency response considerations may limit the extension of the method for very thin sections. The instrument is based upon the principle that sections, when driven by pulses of vibratory energy, resonate at frequencies dependent upon the thickness of the section.
Date: June 28, 1960
Creator: Lambert, T.G.
System: The UNT Digital Library