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Hazards Summary Report for the SM-1 Core Temperature and Flow Instrumentation: Task XIV
Abstract; This technical report describes the changes in the SM-1 incurred by the experiment, Core Temperature and Flow Instrumentation (Task XIV), and evaluates the possible hazard involved in these changes. Temperature and flow measurements will be taken on a Task XIV instrumented stationary fuel element, instrumented control rod fuel element and other selected points in the SM-1 core to provide data on the core steady state and transient performance. The hazards evaluation consists of a nuclear evaluation, thermal and hydraulic analysis, description of tests to be performed, and discussion of containment integrity and maximum accident considerations.
Date:
March 30, 1961
Creator:
Coombe, J. R.; Brondel, J. O.; Lee, D. H. & Matthews, F. T.
System:
The UNT Digital Library
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 the SM-1 Core II With Special Components
Abstract: This technical report describes the changes incurred in the SM-1 by the insertion of the SM-1 Core II and special components. The special components consist of impact specimens, a boron gradient rod, SM-2 elements, a PM-1-M element, and high burnup SM-1 Core I elements. The change in hazards, due to operation of SM-1 with Core II and the special components is evaluated. The analysis indicates there is no change in hazards.
Date:
March 30, 1961
Creator:
Coombe, J.; Lee, D.; Segalman, I. & Robertson, R.
System:
The UNT Digital Library
The Cold Pressing of Sinterable UO₂
The intent of this work was to explore more fully the pressing of sinterable UO2 powders into cylindrical compacts in the hope that a more precise prediction of green density in terms of powder properties, pressure, and geometry could be evolved.
Date:
March 27, 1961
Creator:
Levey, R. P., Jr.
System:
The UNT Digital Library
Final Design Report: DR-1 Gas Loop
Report describing the performance, fission product tolerance, design, and costs of the DR-1 Gas Loop, which is an in-reactor test facility.
Date:
March 1961
Creator:
Baars, R. E.
System:
The UNT Digital Library
SM-2 Core and Vessel Design Analysis (Vol. 1)
Design analysis of the SM-2 core and vessel from work performed during 21 months.
Date:
March 8, 1961
Creator:
unknown
System:
The UNT Digital Library
SM-2 Core and Vessel Design Analysis (Vol. 2)
SM-2 core and vessel design analysis.
Date:
March 8, 1961
Creator:
unknown
System:
The UNT Digital Library
SM-2 Core and Vessel Design Analysis (Vol. 3)
SM-2 core and vessel design analysis.
Date:
March 8, 1961
Creator:
unknown
System:
The UNT Digital Library
Plutonium Spike Fuel Elements for the Plutonium Recycle Test Reactor: Part 1 - The Mark 1-G
Report describing "[t]he fabrication of of the first aluminum-plutonium spike enrichment fuel elements for the Plutonium Recycle Test Reactor (PRTR) at Hanford" Laboratory (p. 2).
Date:
March 1961
Creator:
Freshley, M. D.
System:
The UNT Digital Library