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
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 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