UNT Libraries Government Documents Department - 12 Matching Results

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Advanced Indirect Cycle Water Reactor Studies for Maritime Applications: Part 4. Steam Driven Coolant Pumps

Description: Fourth part of the "final report of a study directed toward the evolution, design, and demonstration of the principle design features of interim indirect cycle water cooled and moderated nuclear power plants which will be useful in early cooperative programs between the Atomic Energy Commission and the United States maritime industry" (p. i).
Date: October 23, 1961
Creator: Combustion Engineering, inc. Nuclear Division.
open access

Cost Estimate for the Food Irradiation Reactor

Description: Study conducted for the U. S. Army Reactors Branch of reactors for the irradiation of food.
Date: August 23, 1956
Creator: Jaffe, R. J.; Larson, A. M., Jr.; Leyse, C. F.; Mason, E. E. & Sliger, R. W.
open access

Engineering Test Reactor Critical Facility Control System Manual

Description: This report consists of the description, drawings, connections, and schematics of the various control elements that make up the control system of the Engineering Test Reactor Critical Facility (ETRC).
Date: June 23, 1961
Creator: Meichle, F. A.
open access

Investigation of 17-4 PH Steel Components Used in SM-1, SM-1A, PM-2A Reactor Plants

Description: Abstract: This technical report covers the investigation of 17-4 PH steel components used in the SM-1, SM-1A and PM-2A nuclear power plants, which consist of control rod drive racks, pinions, seal shafts and associated parts. Evidence supporting the continued use of 17-4 PH steel in these applications is presented. Alco's current procurement and processing specifications for 17-4 PH steel are included. The evidence presented is in the form of stress calculations, test and environmental data and… more
Date: January 23, 1962
Creator: Haraway, E. S. & Saccocio, R. M.
open access

Pyrolysis of Hexadecafluoroheptane

Description: "The studies of this report were made to indicate the thermal stability at elevated temperatures of fluorocarbons similar to the hexadecafluoroheptane" (p. 4).
Date: September 23, 1949
Creator: Walker, D. V. & Gibson, J. D.
open access

SM-1 Reactor Vessel Closure Stud Investigation

Description: Abstract: This report presents metallurgical .analyses and corrosion tests conducted to determine :causes of failure of two SM- 1 reactor vessel studs due to fracture in the threaded areas, after 23 months' operation (March 1959). Conclusions of corrosion tests are: (1) failure of the studs was caused by stress corrosion cracking, (2) contributing factors to failure of the studs were improper control of heat treatment of the studs and absence of treatment for stress relief after thread grindin… more
Date: March 23, 1962
Creator: Reali, D. L.
open access

Structural Evaluation of Underground Waste Storage Tanks

Description: To set forth limiting values of internal vapor pressure and effective liquid specific gravity which will permit the maximum utilization of the existing underground waste storage capacity. It is also intended to describe briefly the elements which could contribute to ultimate failure.
Date: June 23, 1955
Creator: Smith, Edgar F.
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