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Annealing of crystal distortion in irradiated graphite

Description: From introduction: "As part of the program for improvement of graphite, the structural characteristics of graphite have been studied to determine the relation between physical and structural changes during irradiation."
Date: 1955
Creator: Austin, Alfred E. & Harrison, Ralph J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Investigation of KW reactor incident

Description: The new KW reactor was placed in operation on January 4, 1955, and had been running at relatively low power levels for only 17 hours when it was shut down because of a process tube water leak which appeared to be associated with a slug rupture. After several days of unrewarding effort to remove the slugs and tube by customary methods, it developed that considerable melting of the tube and slugs had taken place. It was then evident that removal of the stuck mass and repairs to the damaged tube c… more
Date: February 11, 1955
Creator: Sturges, D. G.; Hauff, T. W. & Greager, O. H.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Interim report, production test-105-522-E, examination of pile process tube removed from 100-B and 100-H Piles

Description: This report covers the examination of nine process tubes, five tubes from B Pile and four from H Pile. Four of the tubes from B File were removed because they were leaking and the fifth was removed because it contained a stuck ruptured slug. Tube 2681-H was removed for graphite mining, tube 2852-H was removed under PT 313-105-14M ``In-Pile Evaluation of 63-S Aluminum Process Tubes,`` and two tubes were removed from channel 0961-H under PT 105-506-E, ``Recirculation of Pile Cooling Water.`` Visu… more
Date: February 10, 1955
Creator: Strege, D. E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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The use of ALUM and activated silica for 100 Area process water coagulation. Final report

Description: Production rates of the Hanford reactors can be increased in proportion to the quantity of process cooling water which can be supplied to them. This water must be of such a quality that slug and tube corrosion rates are acceptable, the gross activity of the effluent water must not be excessive, the concentration of specific radioactive isotopes constituting a radiological hazard must be minimized, and the film formation rates should be as low as possible. In the Hanford water treatment process,… more
Date: July 15, 1955
Creator: Woods, W. C. A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Reduction of rear face Zn{sup 65} activity

Description: This report discusses two methods which have been considered to reduce the rear face activity. The first involves the use of a solids purge to scour out the activity, and the second employs the use of a chromic acid purge to put the activity into solution. Solids purging is found to be ineffective in reducing rear face activity levels. A chromic acid purge conducted at 60 C for 1/2 hour can be expected to reduce the Zn{sup 65} activity level about five fold without injuring the reactor or causi… more
Date: January 31, 1955
Creator: de Halas, D. R. & Gay, R. H.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Interim report, Poison splines flexible control system

Description: This report discusses a system which has been conceived whereby additional flexible reactivity control in the production reactors can be achieved by introducing neutron absorbers contained in thin flexible metal strips between the slugs and the process tube wall. These splines are potentially attractive in that it is possible they could be used to provide additional flexible control during operation as well as temporary control during outages.
Date: November 3, 1955
Creator: Morris, W. J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Water treatment modifications to present areas

Description: It is the purpose of this document to review and up-date the previously presented scope basis for the activated silica installations in light of the existence of the Phase I portion and the present expected water flow requirements of Project CG-558. It is the further purpose to outline the recommended scope bases for the sulfuric acid addition system for pH correction at all areas.
Date: January 26, 1955
Creator: Pearl, W. L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Review of feasibility of high temperature full pile graphite burnout test

Description: The program of the Pile Graphite Studies Unit for the past two years has been directed toward relaxed graphite specifications. The main emphasis in these studies has been on the feasibility of higher permissible maximum graphite temperatures and higher percentages of helium in the gas systems. The success of this program is evidenced by the potential pile power levels permitted by present process specifications. The present graphite Process Specifications will not permit heat generation associa… more
Date: January 5, 1955
Creator: Curtiss, D. H.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Tube Power Limits -- Past, Present and Future

Description: During the history of operation of the Hanford reactors, several methods have been utilized to establish an outlet water temperature or ``Panellit`` limit based on the stability of water flowing through the process tubes. These methods have been known as ``Excess Header Pressure Limits,`` ``Trip Before Boiling Limits,`` and the most recent, ``Trip Before Instability Limits.`` Each new concept vas accepted only after considerable experimental data had proved the new method to be safe and operati… more
Date: May 31, 1955
Creator: Carbon, M. W. & Gilbert, W. D.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Final report -- PT-105-514-A, Installation of thermocouples in process channels

Description: This document discusses a production test which was written when the piles were operating under a graphite temperature limit of 410 C. Operation was controlled by as-read temperatures of the originally installed G thermocouples, by thermocouples installed on vertical safety rod thimbles, and by thermocouples in graphite cylinders installed in the C test holes. Since the thimble thermocouples were to be removed under the Ball 3X program, it was planned to install thermocouples in some of the pro… more
Date: August 8, 1955
Creator: Greenfield, H. H.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Hanford Atomic Products Operation monthly report, August 1955

Description: This document presents a summary of work and progress at the Hanford Engineer Works for August 1955. The report is divided into sections by department. A plant wide general summary is included at the beginning of the report, after which the departmental summaries begin. The Manufacturing Department reports plant statistics, and summaries for the Metal Preparation, Reactor and Separation sections. The Engineering Department`s section summarizes work for the Technical, Design, and Project Section… more
Date: September 27, 1955
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Interim report, Production Test 105-522-E, Examination of pile process tubes removed from 100-C, D and F piles

Description: This report covers the examination of thirteen process tubes seven from F Pile, three from C Pile and three from D Pile. Five of the thirteen tubes were removed because they were leakers, four from F Pile and one from C Pile. One tube from F Pile and one from D Pile were removed. Reactor Section had requested the removal of two from F Pile to check for external corrosion. Two tubes, small diameter old pile annulus, were removed from C Pile under PT 105-519-E, ``Raising Permissible Outlet Water … more
Date: March 17, 1955
Creator: Strege, D. E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Attenuation properties of Hanford pile shield materials

Description: This report discusses an extended program of measurements has been carried out at Hanford to determine the attenuation characteristics of various concretes which might be used as inexpensive yet efficient shields for large, stationary, production piles. The original Hanford piles have biological
Date: September 1, 1955
Creator: Bunch, W. L. & Tomlinson, R. L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Nuclear metallurgy lectures: Chapter 5

Description: In a preceding lecture all the components necessary to secure a controlled nuclear chain reaction were discussed. The business at Hanford is to use these components in the most efficient manner possible to manufacture the desired products of irradiation - the primary product being Pu. In this lecture of the variables of such operation are considered.
Date: May 13, 1955
Creator: Lang, L. W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Hanford Atomic Products Operation monthly report, December 1954

Description: This document presents a summary of work and progress at the Hanford Engineer Works for December 1954. The report is divided into sections by department. A plant wide general summary is included at the beginning of the report, after which the departmental summaries begin. The Manufacturing Department reports plant statistics, and summaries for the Metal Preparation, Reactor and Separation sections. The Engineering Department`s section summarizes work for the Technical, Design, and Project Secti… more
Date: January 25, 1955
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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High Radiation Levels at the Discharge Faces of the Reactors

Description: Undesirably high radiation dosage rates are being encountered in the discharge areas during reactor outages. This is costly to operations in terms of burn-out time, extra work crews, and extended outages require to complete scheduled work. Significant savings in operating costs would be realized if the rear face radiation levels could be reduced during shutdowns. As a first step towards this some measurements have been made to identify and locate the major sources of this radiation. These resul… more
Date: January 4, 1955
Creator: Greene, M. C.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Secondary corrosion barriers: Application

Description: A program to develop a new fuel element was initiated at Hanford in 1951. A survey of the possible methods of making such a fuel element was completed and a document listing all possible lines of research was written. The problem was outlined as it appeared at that time; various developments which have occurred subsequently have changed this problem to a greater or lesser extent. Essentially the problem concerned the development of a fuel element which would not fail or would fail in a slow and… more
Date: July 20, 1955
Creator: Evans, E. A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Hanford Atomic Products Operation monthly report, July 1955

Description: This document presents a summary of work and progress at the Hanford Engineer Works for July 1955. The report is divided into sections by department. A plant wide general summary is included at the beginning of the report, after which the departmental summaries begin. The Manufacturing Department reports plant statistics, and summaries for the Metal Preparation, Reactor and Separation sections. The Engineering Department`s section summarizes work for the Technical, Design, and Project sections.… more
Date: August 26, 1955
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Travel to FMPC for the meeting of the Thorium Working Committee. Trip report, September 20, 1955

Description: A meeting of the Thorium Working Committee was held at FMPC on September 20, 1955. The current status of the thorium production program was discussed and a limited development and evaluation program was outlined which it is felt will (1) clear up some of the more important question marks in thorium metal quality and (2) develop a more satisfactory method for processing solid metal scrap. The basic parts of this immediate program are (1) SRL would evaluate ingot sections of as-cast double arc-me… more
Date: October 10, 1955
Creator: Hayes, E. E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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