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Silver - Cadmium - Indium Absorber Development

Description: Abstract: This technical report covers development of an AG-Cd-In alternate absorber section for Army Type SM reactors. It describes the absorber material composition and the geometric configuration. It gives the nuclear and thermal analyses supporting this configuration and a detailed description of the manufacturing practice employed in fabricating the final design component.
Date: June 13, 1962
Creator: Shaw, R. A. & Harris, R. L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Hazards Report for PM-2A Core II

Description: Abstract: This technical report describes the changes incurred in the PM-2A by the planned insertion of PM-2A Core II and the replacement of the startup and check sources. PM-2A Core II components were fabricated to specifications very nearly identical to those of PM-2A Core I. The essential difference in the cores is the boron loading which permits PM-2A Core II to meet a "one-stuck rod criteria" at beginning of life. This core has been subjected to a zero power experiment and loading procedur… more
Date: June 21, 1962
Creator: Coombe, John R. & Stephenson, L. D.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Mid-Year Summary Report October 1, 1960-March 31, 1961 Army Pwr Support and Development Program

Description: Abstract: A cyclic stress analysis of the SM-1 primary system was carried out. Problems encountered in the fabrication of PM-2A Core II and SM-lA Core II are described, and the results of an examination of damaged SM-lA Core I stationary fuel elements reported. A preliminary study of the radiation damage to SM-1 reactor vessel was made and the possibility of annealing the vessel discussed. Performance analyses are presented for five cores: SM-1 Core, SM-1 Core 1 rearranged and spiked, SM-1 Core… more
Date: June 2, 1961
Creator: Hoover, H. L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Investigation of Local Boiling of SM-1

Description: Abstract; SM-1 Reactor Core I Rearranged and Spiked, and Core II with Special Components were analyzed under various off-design conditions to induce nucleate boiling. The steady state code, STDY-3, written for the thermal analysis of pressurized water cores, was employed for the analysis. The code performs a complete steady state parallel channel thermal analysis for both nominal and hot channels. Thermal characteristics of individual elements were investigated while changing the parameters of… more
Date: June 20, 1961
Creator: Bradley, P. L.
Item Type: Refine your search to only Report
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.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

SM-1 Research and Development Program : Final Report on Fission Product Activity in the SM-1 Primary Coolant, Task XIII

Description: Abstract: Fission product measurements were made on the SM-1 primary coolant. The airborne activity observed during the sampling of the primary system was identified. An analysis was made on the primary coolant for alpha activity and on the secondary water for fission production iodine.
Date: June 30, 1959
Creator: Hasse, Robert A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Extended SM-2 Critical Experiments : CE-2

Description: Abstract: This technical report contains a description and results of a second series of critical experiments performed on the SM-2 core mock-up, as additional to the first series of experiments reported in APAE No. 54. The SM-2 core mock-up contains 36.4 kg U-235 and and estimated 67.9 gm B-10. The equivalent diameter and the active height are about 22 in.; the metal-to-water volume ration is 0.344. Data is presented on activation, reactivity, and stuck rod measurements. All measurements were … more
Date: June 30, 1961
Creator: McCool, W. J.; Robinson, R. A.; Weiss, S. H.; Raby, T. M.; Schrader, E. W. & Walthousen, L. D.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Thermal Analysis of SM-1 Core III

Description: Abstract This technical report covers the thermal analysis performed on the SM-1 Core III for both steady state and transient conditions is reported. SM-1 Core III will be used as a test for Type 3 elements in a PM-2A Core. The steady state analysis indicated minimum departure from nucleate boiling ratios (DNBR) for both design and scram conditions above the minimum criteria of 1.5. Local nucleate boiling was noted in the hot internal channels and lattice passage at scram power conditions. Loss… more
Date: June 29, 1962
Creator: Davidson, S. L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

The Development and Testing of UO2 Fuel Systems for Water Reactor Applications: Summary Report, July 1, 1961 - June 15, 1962

Description: From introduction: "The work described in this report represents the Joint United States - European Atomic Energy Community effort which is in keeping with the spirit of cooperation in contributing to the common good by the sharing of scientific and technical information and minimizing the duplication of effort by the limited pool of technical talent available in Western Europe and the United States."
Date: June 1962
Creator: Murtha, B. E. & Chernock, W. P.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Sodium Mass Transfer - I: Test Loop Design

Description: From abstract: "This report presents the design, fabrication, assembly, operating procedures, and start-up data for six experimental test loops to examine the effect of steel exposed to sodium at temperatures as high as 1300 F."
Date: June 1962
Creator: Lockhart, R. W.; Billuris, G. & Lane, M. R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Prediction of the Critical Heat Flux in Forced Convection Flow

Description: From summary: "A superposition model is developed to predict the critical heat flux in forced convection flow. The model is applied to available experimental results in boiling water flows and good agreement is obtained between the model and test data over the multitude of geometries, flow rates, pressures, and fluid enthalpies tested to-date."
Date: June 20, 1962
Creator: Levy, S.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Simplified Power Conversion: Unit Study

Description: From abstract: "This report presents the results of a feasibility study on a simplified power conversion unit primarily for use with nuclear, steam power plants for military applications."
Date: June 1962
Creator: Clark, P. M.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Comparison of Two Sodium-Cooled, 1000 MegaWatt Fast Reactor Concepts: Task 1 Report of 1000 MegaWatt Liquid Metal Fast Breeder Reactor Follow-On Work

Description: From introduction: "The development of one or more nuclear steam supply system concepts, with certain trade-off studies to aid in the definition of these concepts. The selection of a reference concept for further study."
Date: June 1968
Creator: General Electric Company
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Thermal Expansion of Rare Earth Metals

Description: High temperature dilatometric investigation of the rare earth metals undertaken as part of a broad program of study of these elements, the ultimate goal being better understanding of metals in general.
Date: June 1956
Creator: Barson, Fred; Legvold, S. & Spedding, F. H.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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