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Urine Analysis for Tritium Oxide

Description: This report analyzes a procedure based on the production of acetylene from the active water, with subsequent measurement of the ionization caused by the tritium beta particle. This eliminates the troublesome absorption on the chamber walls when hydrogen is used, and provides a rapid method for the preparation of the urine samples.
Date: July 27, 1949
Creator: Healy, J. W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

The Critical Mass of a Spherical Reactor with Variable Intrinsic Buckling

Description: 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 suspensi… more
Date: April 28, 1949
Creator: Muller, G. M.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Application of Plastic Bags and Sheeting for Operation and Maintenance Across a Contamination Barrier

Description: The following document describes the usage of Vinylite or plastic sheeting for operation and maintenance across a contamination barrier, presenting ecological advantages, photos of special equipment and techniques used during procedure, and the purpose of eliminating open air transfer in contaminated area.
Date: 1952
Creator: Moulthrop, H. A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Monitoring Survey : Richland to Arco, Period May 9-11, 1952

Description: This report follows an investigation of a cargo truck found contaminated by various radioactive material on a routine trip from Arco, Idaho to the Hanford plant on May 8, 1952. The report analyzes the truck's route in an attempt to find the location of the contaminating region.
Date: June 20, 1952
Creator: Honstead, J. F.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Graphite Sample Boring from Process Channels : Final Report, Production Test 105-389-P

Description: The following report records a total of forty-nine graphite core samples that have been bored from process tube blocks in the Hanford piles with the intention to provide results to indicate that core boring is an entirely practical operation over bore scraping in obtaining powder samples.
Date: July 10, 1951
Creator: Cole, J. B.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Examination of Masonite in Biological Shield : Interim Report

Description: 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.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Minutes of Criticality Instrumentation Meeting Hanford Atomic Products Operation August 17 and 18, 1959

Description: At the request of the Hanford Operations Office of the Atomic Energy Commission, a criticality instrumentation meeting was held at Hanford on August 17 and 18, 1959. The purposes of the meeting were: (a) to review types of criticality control and/or alarm instrumentation at each site, their problems, shortcomings and potential obsolescence; (b) to discuss instrumentation in the area if approaching criticality; and (c) to consider for material balance purposes, the feasibility of devising instru… more
Date: September 16, 1959
Creator: Brown, C. L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Filtering Abrasive-Wheel Uranium Cuttings

Description: Extremely radioactive particles result from the abrasive wheel cutting of irradiated fuel elements in the cut-off cell located in the 327 Building. Due to the use of water during the cutting operation these particles are in suspension and must be removed before the liquid can be discharged to the liquid waste tanks in the 340 building. The filters presently employed in the cell total activity discharged to the 340 Building tanks is attributed to the particles which pass these filters. With the … more
Date: September 18, 1959
Creator: Postma, A. K. & McCorrmack, J. D.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Plutonium Oxalate Disk Filter and Filter Media Studies

Description: Presently rotary drum filters are being used for plutonium oxalate slurry filtration in the 234-5 Building. Changing of the filter cloth used on a rotary drum is a time consuming operation which involves ever increasing radiation exposure to maintenance personnel. Consequently, studies were conducted in the 321 Building on a disk type filter which could be adapted for simple and quick ("one-nut") replacement of the filter medium.
Date: October 19, 1959
Creator: Rey, George
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Critical Tests for PRT Reactor

Description: This document authorizes the performance in accordance with the specifications noted, the PRTR Critical Tests described herein. The experiments described have the following objectives:
Date: July 1, 1960
Creator: Triplett, J. R.; Anderson, J. K.; Peterson, R. E.; Regimball, J. J.; Russell, J. T.; Schmid, L. C. et al.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Plutonium Recycle Critical Facility: Final Safeguards Analysis Supplements

Description: Report containing supplementary material for "Plutonium Recycle Critical Facility, Final Safeguards Analyses." This material expands upon previously supplied safety information and resolves previously unreviewed safety questions. Appendix begins on page A.1.
Date: October 1964
Creator: Swanberg, F.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Protective Clothing Monitoring System

Description: Report describing the development and installation of an automated conveyor-type laundry system for the purpose of monitoring laboratory clothing for beta-gamma contamination.
Date: August 1, 1963
Creator: Rankin, M. O. & Spear, W. G.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

The Hanford Isotopes Production Plant Engineering Study

Description: Report presenting the conceptual design, estimates of capital and operating costs, and details of the operation of a plant "capable of high volume production of encapsulated heat sources" (p. 3) of radioisotopes Sr90, Cs137, Ce144, and Pm147.
Date: July 1963
Creator: La Riviere, J. R.; Michels, L. R.; Riches, H. C.; Rohrmann, C. A.; Smith, C. W. & Swift, W. H.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

The Effect of Deionized Water on the Reactor Effluent Activities: Part 2 - Zirconium and Aluminum Clad Fuel

Description: Report containing experimental data testing the hypothesis that aluminum reactor tubes were "the site of most radioisotope production in the deionized water cooled system" and that zirconium tubes provided "only nominal participation" (p. 2).
Date: October 1964
Creator: Silker, W. B. & Thomas, C. W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

PRTR Fuel Element Nuclear Safety

Description: A study of the nuclear safety in the storage and transportation of PRTR fuel elements has been made. This study was based on 7-rod clusters of plutonium-aluminum allow fuel elements containing 1.8 per cent Pu by weight. Each cluster is 7 feet 4 inches in length and contains 270 grams plutonium. Drawings of the "New Fuel Storage Pit" (H-3-11030) have been reviewed for nuclear safety. Nuclear safety criteria for the design of a lead shielded fuel transfer cask as well as criteria for the storage … more
Date: March 30, 1959
Creator: Ketzlach, N.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

The Nuclear Safety of Fissile Materials

Description: Whenever fissile materials are handled in significant quantities such as in fuel element fabrication, separation processes, or in exponential and/or critical experiments a potential criticality hazard exists. The usual procedure which is followed by those persons conducting critical mass experiments is to either place the potential reactor in a heavily shielded cell or to conduct the experiments remotely in which case distance provides a measure of safety in the event of an unscheduled radiatio… more
Date: 1959-02-11?
Creator: Clayton, E.D.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Random Loading of E-Metal Dissolver

Description: Nuclear safety in the dissolution of irradiated 0.95 U235 enriched fuel has been investigated. In particular, critical conditions of fuel of this enrichment in a 52-inch diameter dissolver crib were studied. Since a crib this size is not safe by geometry, dissolution procedures as well as maximum safe batch sizes were analyzed. Uranium-water lattices are normally studied in systems in which rods are uniformly dispersed in the moderator. The results of such a study for 1.34-inch diameter solid … more
Date: February 25, 1959
Creator: Ketzlach, M.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Trough-Time Dissolver

Description: Designing a dissolver safe for up to 5 per cent U.235 enriched NPF's and having a one a ton per day capacity is a fundamental problem of Hanford NPF Program. Two basic design concepts have so far evolved, both of which employ a recirculating system in which the fuel elements are placed in the critically safe geometry separated from the bulk of the solution in another vessel. In one concept the fuel elements are charged to a set of geometrically safe cylinders or tubes and solution is circulated… more
Date: June 26, 1959
Creator: McKee, R.W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Design Criteria for PRTR High Pressure Loop Project CAH-841

Description: The PRTR pressure loop is an experimental facility to be installed in the Plutonium Recycle Test Reactor, Building 309, for use in testing the feasibility of reactor cooling systems utilizing high pressure water or steam as the coolant. It will furnish operating experience with such systems and serve to test fuel elements and components designed to operate in such environments.
Date: October 15, 1959
Creator: Fox, J. C.; Jakub, M. T. & Kelly, W. S.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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