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Hazards Report for Step Transient Loading Tests on the SM-1 : Task XII

Description: Abstract: This technical report evaluates hazards involved with SM- 1 plant response and system performance tests (Task XII), to determine the response of the SM-1 plant to step electrical and steam load changes. The report describes the changes in plant equipment and operating procedures for this task and evaluates these changes for possible additional hazards to those described in APAE No. 2, Revision 1, "Hazards Summary Report for the Army Package Power Reactor SM-1."
Date: February 1, 1962
Creator: Pomeroy, D. L.
Partner: UNT Libraries Government Documents Department
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The Influence of Design and Production Parameters on Fabrication Costs of Nuclear Reactor Fuel Elements

Description: The objectives for this study were to determine fuel fabrication and assembly costs in a large nuclear power industry for several reactors, fuel rod sizes, and fuel materials.
Date: November 1, 1961
Creator: Stein, P. E.; Ayers, A. C.; Braatz, R. J.; Bradford, C. M.; Holt, V. D. & Mattie, G. P.
Partner: UNT Libraries Government Documents Department
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Design, Fabrication, and Irradiation of Superheat Fuel Element SH-4B in VBWR

Description: From abstract: "The design, fabrication, and irradiation results are described for a 0.028 inch thick 304 stainless clad fuel element (SH-4B) exposed in the Vallecitos Boiling Water Reactor loop under superheat conditions."
Date: September 1, 1961
Creator: Spalaris, C. N.; Boyle, R. F.; Evans, T. F. & Esch, E. L.
Partner: UNT Libraries Government Documents Department
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Hazards Report for Insertion of the PM-1-M-2 Element in the SM-1 Core II

Description: Abstract: This technical report describes the Martin Co. PM-1-M-2 test element and analyzes the potential hazard incurred by its inclusion in the SM-1 Core II. A nuclear analysis develops power distributions and reactivity effects. Hydraulic and thermal analyses develop anticipated burnout heat flux ratios. An evaluation of the risk involved with the inclusion of this element is presented. In view of the narrow margin by which the PM-1-M-2 test element meets the minimum burnout ratios as def… more
Date: September 1, 1961
Creator: Coombe, J. R.; Scoles, J. F.; Brondel, J. O. & Lee, D. H.
Partner: UNT Libraries Government Documents Department
open access

Heat Transfer Coefficients with Annular Flow During "One-Through" Boiling Water to 100 Per Cent Quality at 800, 1100, 1400 PSI

Description: From introduction: "Once-Through boiling of water to 100 per cent steam quality was successfully accomplished. Results of Departure from Nucleate Boiling, transition, and film boiling tests are presented."
Date: May 1, 1961
Creator: Polomik, E. E.; Levy, S. & Sawochka, S. G.
Partner: UNT Libraries Government Documents Department
open access

Suitability of Inconel for Corrosion Protection on Water Side of Sodium Component Steam Generator

Description: Abstract; The heat exchanger and steam generator for the U.S. Atomic Energy Commission Sodium Components Project will be constructed entirely of type 316 stainless steel. Because of the susceptibility of this alloy to stress corrosion cracking, it is proposed to clad all areas of the steam generator with Inconel where the stainless steel will be exposed to water and steam. This report includes a discussion of the work by numerous investigators that justify the selection of Inconel for this se… more
Date: March 1, 1961
Creator: Phillips, Laurence E. & Vawter, Frank J.
Partner: UNT Libraries Government Documents Department
open access

Experiments and Analysis for SM-1 Core II With Special Components

Description: Abstract: This technical report contains a summary of analytical and experimental work performed on SM-1 Core II, with special components is presented. The effects of these special assemblies upon power distribution and core reactivity were calculated and compared to experimental measurements. A thermal analysis was conducted to determine steady state and transient performance of the special test components of the core as well as some of the hotter standard Core II components. Experimental work… more
Date: January 1, 1961
Creator: Lee, D. H.; Robinson, R. A. & Segalman, I.
Partner: UNT Libraries Government Documents Department
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Scale "Up or Down" Analysis for Prototype Test

Description: Introduction: In conjunction with the final design and development of a 70 MW sodium intermediate heat exchanger and a sodium steam generator, an analysis is required which can be used as a basis for a determination to scale up or scale down the designs. Included in this analysis are those considerations leading to the recommendation of the best prototype test unit and to some of the limits imposed on scaling up or down when considering future applications of designs other than those actually … more
Date: May 1, 1960
Creator: Alco Products (Firm).
Partner: UNT Libraries Government Documents Department
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A Survey of the Effects of Neutron Irradiation on the Impact and Other Mechanical Properties of Pressure Vessel Steels for the SM-2 Reactor

Description: Abstract: This technical report summarizes the data obtained in a recent literature survey conducted to determine the effects of neutron irradiation on the impact and other mechanical properties of both ferritic steels and austenitic stainless steels. The survey was primarily aimed at obtaining sufficient data on the behavior of pressure vessel steels at high integrated neutron flux levels in order that a reference material of construction could be selected for the SM-2 (APPR-1B) reactor vesse… more
Date: April 1, 1960
Creator: Kelleman, Richard William.
Partner: UNT Libraries Government Documents Department
open access

Halogen Collector Test Program

Description: Report documenting the Halogen Collector Test program, which was undertaken to provide "methods of removing trace quantities of radioactive iodine from an air stream" (p. 1). The report includes designs of the program and the test facility, test results, analysis of these results, and encountered problems. Appendices begin on page 38.
Date: March 1, 1960
Creator: Arthur D. Little, Inc.
Partner: UNT Libraries Government Documents Department
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