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Reactor process flow technical data

Description: A computer program is being developed for the solution of general system flow problems. As a complement to this program, a summary of the process system has been prepared. This assembles information from a number of different reports, drawings and technical notebooks into one place for easy use and reference. It is expected that the information contained in this report will be of use in safety and design studies of these process systems. This report presents current values of the reactor flow characteristics and the primary pumping system characteristics. It also presents the process piping system and the basis for a computing program for calculating system pressure drops.
Date: February 15, 1962
Creator: Jones, S.S.; Morrissey, J.E. & Manuel, J.L.
Partner: UNT Libraries Government Documents Department

Graphite burnout, interim report on IP-25-A (PT-105-532-E)

Description: Graphite reacts with such gases as CO{sub 2}, O{sub 2}, or water vapor to form gaseous oxides of carbon. In the case of CO{sub 2}-graphite interaction, the reaction rate is not significant until about 550 C. Water oxidizes graphite, very roughly, three times faster than CO{sub 2}. Air will oxidize graphite appreciably at temperatures below 500 C. Graphite removal from Hanford reactors is very important, since graphite is used both as a structural support and a moderator for neutrons. Griggs has shown that small graphite samples oxidized to 10 per cent weight loss had only about one-half their original compression strength. Hence, the longevity of the reactors depends to a great extent on maintaining a low graphite oxidation rate. A means of monitoring the extent of graphite loss, i. e., the burnout rate, is necessary to establish future reactor operational standards. Presently, weighed samples of reactor grade graphite are placed along the length of an empty process channel in each reactor. Thus, a sample is exposed to the reactor`s ambient conditions of power level, moderator temperature, and gas composition. This program was initiated in the vicinity of June, 1953 by Woodley. This report presents data on graphite burnout obtained from in-reactor experiments authorized under IP-25-A (PT-105-532-E) from August, 1957 to January, 1960. Burnout rates are obtained by a direct measurement of the weight loss of control graphite samples exposed to the reactor atmosphere.
Date: March 15, 1960
Creator: Ryan, B.A. & Halas, D.R. de
Partner: UNT Libraries Government Documents Department

Investigation of impulsively loaded pressure vessels

Description: Explosion containment vessels for containing from 2,000 to 3,000 five ton nuclear explosions are considered. Analysis methods appear adequate and lowest weights using the most advanced materials available in the next five years are projected.None of these materials can be fabricated today and all require extensive development. Present material technology limits the choice of materials and defines the weight. The addition of safety factors and fixtures (nozzles, etc.) will add to this weight considerably, and may well radically alter the vessel response. Improvements in the strength weight ratios of metals and glasses over those considered in this report do not appear reasonable at this time. Winding schemes to utilize the high strength of steel wires and somehow maintain a reasonable thickness appear to offer the most promise. A `ductile` beryllium would of course offer vast improvement, but no indications that this is being developed have appeared and all presently known beryllium is much too brittle.
Date: October 15, 1963
Creator: Brown, N.; Cornwell, R.; Hanner, D.; Leichter, H. & Mohr, P.
Partner: UNT Libraries Government Documents Department

Control rod studies (Tory II-C)

Description: This memorandum outlines the area of interest in connection with the SSBN launch application, on modification of the Tory II-C control rod system; and suggest a plan of development of information. Because of the very limited space for overall missile length, little room is available for control rod motion upstream from the core. Shortening the rod stroke, and the total length occupied by control rod mechanism., becomes very desirable. Changes in the actuator and linkage mechanism will clearly help, and should be investigated. However, this is concerned only with neutronic aspects.
Date: November 15, 1962
Creator: Hadley, J.W.
Partner: UNT Libraries Government Documents Department

Evaluation of low assay Pu-238 oxide for use in fabrication of plasma-fired microspheres

Description: The desirability of evaluating low assay plutonium-238 ({approximately}23% Pu-238) oxide was discussed with AEC personnel during a meeting at Germantown on July 6, 1967. In September, 1967 a sample of this material was furnished to Mound for evaluation. This evaluation was to be completed on a schedule which would not interfere with production of material for the SNAP programs, and was to include characterization of the oxide feed, and preparation and subsequent characterization of plasma-fired microspheres according to SNAP-27 procedures. Authorization to perform this work was received from DAO on September 1, 1967.
Date: May 15, 1968
Creator: Madding, R.D. Jr. & Vallee, R.E.
Partner: UNT Libraries Government Documents Department

Reactor outage schedule (tentative)

Description: This single page document is the October 15, 1969 reactor refueling outage schedule for the Hanford Production Reactor. It also contains data on the amounts and types of fuels to be loaded and relocated in the Production Reactor.
Date: October 15, 1969
Creator: Walton, R. P.
Partner: UNT Libraries Government Documents Department

Reactor outage schedule (tentative)

Description: This single page document is the September 15, 1969 reactor refueling outage schedule for the Hanford Production Reactor. It also contains data on the amounts and types of fuels to be loaded and relocated in the Production Reactor.
Date: September 15, 1969
Creator: Walton, R. P.
Partner: UNT Libraries Government Documents Department

Reactor outage schedule (tentative)

Description: This single page document is the December 16, 1969 reactor refueling outage schedule for the Hanford Production Reactor. It also contains data on the amounts and types of fuels to be loaded and relocated in the Production reactor.
Date: December 15, 1969
Creator: Walton, R. P.
Partner: UNT Libraries Government Documents Department

Monthly report, November, 1966

Description: This report gives summaries for the reactor plant operations, fuel and target fabrication, technical activities, advanced concepts and planning, and irradiation services. A feature report is included which describes the following: (1) the safety and control rod systems of the production reactors; (2) the problems which have developed with them; and (3) the corrective rod channel renovation and rod modification work which has been accomplished.
Date: December 15, 1966
Partner: UNT Libraries Government Documents Department

MAGNETIC RECORDER FOR NUCLEAR PULSE APPLICATION. Period covered: February 6 to April 5, 1960

Description: The accuracies which can be achieved in analog recording systems are for the most part tape limited. While reasonable variations in tape speed do not directly affect the accuracy, such variaticns result in improper tape tensioning, which in turn results in poor head-to-tape contact. The quality of the tape transport mechanism should be such that the error introduced by improper head- totape contact is less than tape errors. Some additional equipment is necessary in setting up a tape recorder for a given experiment. The amplitude of the input pulse spectrura to the recorder should be adjusted for optimum value and, if possible, the counting rate should be adjusted to obtain good tape utilization. An oscilloscope is probably adequate to satisfy both conditions. (auth)
Date: April 15, 1960
Creator: Burgwald, G.M. & Norton, R.M.
Partner: UNT Libraries Government Documents Department

Feasibility Study of a New Mass Flow System. Period Covered January 1- January 31, 1961

Description: Machining was completed on the s-tube flow element, and a spring, for use at a constant known temperature, was constructed for the flow element. Calculations for geometry factor, detector efficiency, and effective absorption along the useful radiation path were completed for the reed densitometer. The flow rate control was calibrated and performed satisfactorily. Response to step transient changes occurred with a damping constant of about 0.6 and an effective response time of 10 sec. Sources of error in the s-tube flow rate measurements are discussed. (M.C.G.)
Date: February 15, 1961
Creator: Burgwald, G. M.
Partner: UNT Libraries Government Documents Department

Effect of Alloying Constituents on Aluminum Dissolution Rates

Description: In studies of the effect of alloying elements on the rate of dissolution of Al in mercury-catalyzed nitric acid, it was observed that Co, Ni, and Si present at concentrations of 1 to 2% have significant passivating effects. Fe was slightly catalytic. Passivation due to Si was partly overcome by contacting the passive alloy with active, high-purity Al. Increased catalyst concentration improved the rates when Ni and Si were present. Neither approach was effective when Cu was the passivating element. For application to nuclear fuel reprocessing, it is suggested that for minimum reprocessing costs the potentially passive Al alloys not be used in fuel elements or that, failing this, electrochemical activation techniques be applied at the processing plant. (auth)
Date: April 15, 1963
Creator: Fletcher, R. D.; Jacobson, M. E. & Beard, H. R.
Partner: UNT Libraries Government Documents Department

Scope of Chemical Explosive Cratering Experiment

Description: A general description is given of the Pre-Buggy chemical explosive experiments. These experiments consisted of a series of single- and multiple- charge detonations designed to refine our knowledge of channel size as a function of charge spacing, and to obtain data on venting of explosion products from a row of spherical charges detonated in alluvium. A basic series of six single-charge detonations and four multiple-charge detonations of five charges in a row was executed in Area 5 of the Nevada Test Site from November 1982 through February 1983. Each charge contained 1,000 pounds of nitromethane with a La/sup 140/ tracer. Preliminary examination of the results indicates that: (1) When charges were spaced at 1.0 single-charge crater radius, the channel depth and width were larger than the diameter and depth of a single-charge crater. (2) Small increases in spacing resulted in considerable reduction of channel depth and a smaller reduction in width. (3) The channel shape at spacings of 1.5 single- charge crater radii was very uneven. (4) When the ratio of the depth-of-burst to depth-of-crater was about two, the venting of explosion products from a row- charge detonation was less than from single-charge detonations. (auth)
Date: May 15, 1963
Creator: Graves, E.; Wray, W. R. & Pierce, R. B.
Partner: UNT Libraries Government Documents Department

Research and development allocations and plant assistance support, FY-1969

Description: This document describes the scope of research and development assistance work required to meet the program needs for FY-1969 of Douglas United Nuclear, Inc. in the operation of the C, N and K Reactors. The allocation of research and development funds and estimates of work order support for plant assistance work to Battelle-Northwest are consistent with the research and development funding level in FY-1969 and with the estimates described in DUN-4584, ``Research and Development Allocations and Plant Assistance Support, FY-1969,`` C. D. Harrington to F. W. Albaugh (Confidential). As the programs progress, or if program emphasis changes, it may be necessary to make adjustments in the funds allocated to individual programs within the total level of available funds. The distribution of funds to the various programs is summarized in the enclosed tables.
Date: August 15, 1968
Creator: Riches, J.W.
Partner: UNT Libraries Government Documents Department