Suitability of Inconel for Corrosion Protection on Water Side of Sodium Component Steam Generator (open access)

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

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 service. A discussion of Inconel type welding alloys is also included.
Date: March 1, 1961
Creator: Phillips, Laurence E. & Vawter, Frank J.
System: The UNT Digital Library
Hazards Report for Insertion of the PM-1-M-2 Element in the SM-1 Core II (open access)

Hazards Report for Insertion of the PM-1-M-2 Element in the SM-1 Core II

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 defined by Alco Products, Inc., it is recommended that if time permits that critical facility design verification be accomplished. The PM-1-M-2 test element meets the minimum requirements for insertion in SM-1 Core II and in view of the importance of this element to the PM-1 and PM-3A program, should be considered for insertion.
Date: September 1, 1961
Creator: Coombe, J. R.; Scoles, J. F.; Brondel, J. O. & Lee, D. H.
System: The UNT Digital Library
Experiments and Analysis for SM-1 Core II With Special Components (open access)

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

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 discussed includes individual reactivity effects of all the special elements and the total effect of all of the elements. Power mappings were also made and are reported.
Date: January 1, 1961
Creator: Lee, D. H.; Robinson, R. A. & Segalman, I.
System: The UNT Digital Library