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Sodium Mass Transfer - I: Test Loop Design
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.
System:
The UNT Digital Library
Prediction of the Critical Heat Flux in Forced Convection Flow
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.
System:
The UNT Digital Library
Simplified Power Conversion: Unit Study
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.
System:
The UNT Digital Library
VBWR Stability Test Report
Analysis of the stability of boiling water reactors.
Date:
June 1963
Creator:
U.S. Atomic Energy Commission
System:
The UNT Digital Library
Comparison of Two Sodium-Cooled, 1000 MegaWatt Fast Reactor Concepts: Task 1 Report of 1000 MegaWatt Liquid Metal Fast Breeder Reactor Follow-On Work
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
System:
The UNT Digital Library