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Prediction of Thermal-Neutron Fluxes in the Bulk Shielding Facility from Lid Tank Shielding Facility Data

Description: Technical reports details how thermal neutron data from the Lid Tank Shielding Facility (LTSF) at Oak Ridge National Laboratory was used to predict fluxes for the larger Bulk Shielding Facility (BSF) by accounting for geometric differences and neutron self-attenuation within mockups. The study found predictions generally by 12 to 22% higher for distances closer than 60 cm from the reactor, but they are in essentially in agreement at larger distances.
Date: January 12, 1959
Creator: MacKellar, A. D.
Partner: UNT Libraries Government Documents Department
open access

SM-1 Shielding Analyses

Description: Abstract: This technical report analyzes gamma dose rate and neutron measurements in their relation to the SM-1 shield design and is a continuation of previous shielding measurements and analyses reported in APAE-35 and APAE-35 Supplement 2. The data reported herein are spent fuel element and rod drive pit gamma dose rates. An analysis of gamma dose rates off the core midplane is presented and compared with test data.
Date: June 20, 1962
Creator: Stephenson, L. D.
Partner: UNT Libraries Government Documents Department
open access

Shielding Requirements for the Army Package Power Reactor

Description: Abstract. The design, selection, and calculation of the Army Package Power Reactor shielding are described. The APPR-1, a prototype of a package reactor for remote locations, has a primary shield of iron and water. this shield has been adopted to permit fast erection and to provide low transported weight. economically, including transportation cost, the iron water shield is better than a lead water shield and is competitive with a concrete shield for a remote site. Because of the location at… more
Date: May 1, 1956
Creator: Meem, J. L. (James Lawrence). & Fairbanks, F. B.
Partner: UNT Libraries Government Documents Department
open access

Lecture Notes on Reactor Shielding

Description: Report issued by the Argonne National Laboratory discussing the shielding of radiation produced by nuclear reactors. As stated in the introduction, "these lectures will be an attempt to discuss the design of a reactor shield and the solution of the associated shielding problems by simple hand-computing methods" (p. 19). This report includes tables, and illustrations.
Date: March 1959
Creator: Grotenhuis, Marshall
Partner: UNT Libraries Government Documents Department
open access

Startup Testing of the PM-2A Nuclear Power Plant

Description: Abstract: A detailed description of the PM-2A reactor, primary system and instrumentation is presented. A general description of the secondary system and plant arrangement at Camp Century, Greenland is included. The results of the startup physics, shielding, thermal and hydraulics and radiochemistry test are presented. the analysis performed on the shielding and thermal and hydraulic tests is included. The shielding problem at startup and the shielding modification made to the plant are describ… more
Date: March 31, 1962
Creator: McCool, W. J.; Ryan, R. M.; Richards, W. M. S.; Bradley, P. L.; Stephenson, L. D. & Cox, J. F.
Partner: UNT Libraries Government Documents Department
open access

CP-6 Thermal Shield Experiments

Description: A mockup of the Argonne Neutron Production Reactor iron water shield was tested in the Lid Tank Facility. Data are presented from measurements of thermal neutron flux and gamma doses at various distances from the source and with various shield configurations.
Date: December 6, 1952
Creator: Blizard, E. P.
Partner: UNT Libraries Government Documents Department
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