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Safety system for RDA-DC-3

Description: The basis for the safety control system for RDA-DC-3 is set forth in HDC-2462 with revisions as noted here. These conditions are satisfied by an array of safety control components comprising 37 vertical safety rods and 51 ball hoppers (51 total vertical graphite slots) as shown on drawing H-1-21403.
Date: February 18, 1952
Creator: Reed, E. L.; Robinson, T. F. & Roy, G. M.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

History of the project as of February 1, 1951

Description: In 1946, it was recommended, by the district engineer for the War Department, United States Engineer Office, that it was desirable to transfer all of the functions of production to Hanford, a production installation; thereby relieving the Argonne National Laboratory, a research installation, from production duties. This decision was based on the belief by Argonne National Laboratories that the principal problems of production were solved, as a result of a meeting held at Clinton Laboratories, O… more
Date: January 4, 1952
Creator: Reed, G. G. Jr.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Heat transfer studies technical activities report

Description: Discussed activities include: boiling consideration studies, C pile Panellit ranges and orifice sizes, testing of time delay relay, tube water flow studies, extrapolation of pile design data, temperature distributions in cold-sized canned J-slugs, pressure drop film studies, short tube mockup, film formation studies experiment, pile pressure drop increase studies, pile process specifications, loss of pile cooling water study, thermocouple slug, measurement of slug bond coefficients, slug temper… more
Date: April 1, 1952
Creator: Carbon, M. W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Safety control system for RDA-DC3

Description: It is important that the design of the safety control system for RDA-DC3 be firmed up as soon as possible. This is necessary so that the detailed design of the graphite stack and other components can proceed. One design objective for RDA-DC-3 was the use of an all ball system for the safety system. The questionable feature of such a system from a mechanical and operating standpoint is the requirement that the balls be returned to the hoppers in about 10 minutes. This stringent requirement can b… more
Date: January 14, 1952
Creator: Roy, G. M.; Robinson, T. F. & Reed, E. L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Minimum pressure requirements at top of riser -- RDA DC-6, cooling water studies

Description: This report consists of a graph which plots the minimum requirements for the pressure at the top of riser after an electrical power failure verses time after the electrical power failure. Pressure is expressed in pounds per square inch. Points for shutdown of maximum operation and normal operation are given.
Date: February 11, 1952
Creator: Nixon, V. D.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Recommended settings for 105-C trips

Description: This memorandum discusses the engineered safety system which combines the Ball 3-X System with the VSR System. The operation of the system is detailed and settings are recommended for 105-C trips.
Date: September 25, 1952
Creator: Roy, G. M.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Application of Reactor Safeguard Committee Formula

Description: The Reactor Safeguard Committee formula for the allowable minimum distance between a reactor and the public domain is expressed as: r = 0.01{radical}P, where r = radius from reactor in miles, and P = reactor power level in kilowatts. The six plates in this report illustrates the application of this formula for Hanford Works, both for individual reactors and all reactors in an area.
Date: April 22, 1952
Creator: Smith, J. M.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Temperature distribution in a slug

Description: Temperature variations in a slug create problems in stresses, corrosion, and design. As an acid in solving these problems for present and higher power levels, the temperature distribution and anticipated maximum temperatures have been calculated and are presented here. They are based upon theoretical investigations of heat flow in a four inch standard slug. The results of these investigations are presented in this document.
Date: June 24, 1952
Creator: Amos, D. E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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