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Accidental Radiation Excursion at the Y-12 Plant, June 16, 1958: Final Report

Description: This report describes the circumstances leading to the accident, attempts to reconstruct the nuclear reactivity conditions, and reviews the dosimetric means and results which were used to help determine the exposure of affected employees.
Date: September 12, 1958
Creator: Patton, F. S.; Bailey, J. C.; Callihan, A. D.; Googin, J. M.; Jasny, G. R.; McAlduff, H. J. et al.
open access

An Addendum to a Parametric Study of the Gas-Cooled Reactor Concept

Description: From introduction: "This report provides background information regarding the study results presented in the first volume of this report and provides information resulting from the studies made on the gas cooled reactor concept."
Date: March 1, 1958
Creator: Hanford Works
open access

The Alco Products Inc. Criticality Facility : Description and Operation

Description: The Alco Products Criticality Facility, site location, and operating procedures are described in detail, including the handling of fissionable material and the operating procedures for the safe performance of critical experiments.
Date: July 16, 1958
Creator: Noaks, John W.
open access

An Alpha, Beta, Gamma Hand and Shoe Counter - Model 2

Description: Experimental combination hand and shoe counter redesign as a compact, simplified, register readout instrument no larger than the present Five-Fold called Model 2.
Date: June 2, 1958
Creator: Spear, W. G.
open access

Analysis of Extended Zero Power Experiments on the Army Package Power Reactor : ZPE-2

Description: Introduction: This report is principally concerned with analysis of measurements taken on the APPR-1 core during the course of the extended Zero Power Experiments (ZPE-2). The bulk of these measurements are reported in APAE No. 21. There are some additional measurements reported in APAE Memo 115. In addition to the analysis of the ZPE-2 data some re-evaluation has been made of a few of the results obtained from the first set of Zero Power Experiments (ZPE-1). The ZPE-1 measurements are repor… more
Date: May 7, 1958
Creator: Byrne, B. J. & Oby, P. V.
open access

APPR-1: Design, Construction and Operation

Description: "This document includes papers covering technical problems involved in the design, construction and operation of the APPR-1" (p. 4).
Date: November 20, 1957
open access

An Automatic Analyzing Monitor for Reactor Effluent Cooling Water

Description: From objective: "The objective of this work was to design, develop, assemble, and test and automatic analyzing monitor for recording the prominent isotopes in reactor effluent cooling water."
Date: May 1, 1959
Creator: Rieck, H. G.; Ratcliffe, C. A. & Schwendiman, L. C.
open access

A Continuous Water Monitor for Detecting PPM Quantities of Alkali Metals

Description: Abstract: "This report describes a flame photometric system which continuously monitors a process water stream for ppm quantities of alkali metals, and automatically diverts the stream when the contamination exceeds a pre-determined level."
Date: June 20, 1955
Creator: Been, Julian F.
open access

Conversion of UNH to UO3 : Terminal Report

Description: Feasibility of conversion of uranyl nitrate to uranium trioxide by the continuous addition of concentrated uranyl nitrate solution to hot, agitated UO3 powder.
Date: January 10, 1951
Creator: Maness, R. F. & Clagett, F.
open access

Cost Estimate for the Food Irradiation Reactor

Description: Study conducted for the U. S. Army Reactors Branch of reactors for the irradiation of food.
Date: August 23, 1956
Creator: Jaffe, R. J.; Larson, A. M., Jr.; Leyse, C. F.; Mason, E. E. & Sliger, R. W.
open access

Decontamination Program Task II. Volume 1, Contamination and Decontamination in Nuclear Power Reactors

Description: Abstract: A survey of the problem of reactor system contamination by radioactive material and methods that have been employed to remove the material was carried out. Following this survey, an investigation of chemical solutions was undertaken to find one which might be successfully employed in the decontamination of a stainless steel steam generator. From a preliminary screening, the most promising chemical method from the view point of minimum corrosion and maximum decontamination is a caus… more
Date: February 13, 1959
Creator: Zegger, John L. & Pancer, Guyon P.
open access

Decontamination Program Task II. Volume II, Evaluation of Chemical Agents for Nuclear Reactor Decontamination

Description: Abstract: The caustic permanganate-rinse decontamination treatment was investigated. Loop and metallurgical studies were performed to determine optimum operating conditions as well as the metallurgical effects of the treatment. A treatment with 10 percent sodium hydroxide and 5 percent potassium permanganate solution followed by a rinse with a 5 percent ammonium citrate, 2 percent citric acid and 1/2 percent Versene solution was chosen for the decontamination of a stainless steel steam generat… more
Date: February 15, 1959
Creator: Zegger, John L. & Pancer, Guyon P.
open access

Decontamination Program Task II. Volume III, Recommended Procedure for Decontamination of a Stainless Steel Steam Generator

Description: Abstract: A decontamination procedure for a stainless steel steam generator similar to the APPR-1 using a fill-flush application of a caustic permanganate-citrate combination solution is recommended. The isolation of the steam generator is to be accomplished by means of specially designed plugs at the reactor vessel outlet and at the primary coolant pumps. Anticipated results, including corrosion rates and decontamination factors, are presented.
Date: February 13, 1959
Creator: Pancer, Guyon P. & Zegger, John L.
open access

Degassing Sparger Plate Screening Tests

Description: Results of tests to remove fission gases, xenon and krypton, formed during the operation of a nuclear reactor.
Date: September 1958
Creator: Starkweather, D. C.
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