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Determination of Suitable Insulation for a 1-5/16" Helium Filled Annulus in the Orr Helium in-Pile Loop, Design No. 4

Description: Heat loss tests were conducted with six insulation configurations for application in the riser regenerator and auxiliary regenerator sections of the loop. Insulation consisting of ten laminations of 0.003 in. stainless steel shim stock spaced 1/8 inch apart produced a temperature drop across the 15/16 inch annulus of 1200 F with a heat loss of 1.04 KW per foot of 2 inch schedule 40 pipe. The curve of heat loss vs. temperature difference is presented which, with results of similar tests with a 1… more
Date: August 17, 1959
Creator: Knight, R. B. & Helms, R. E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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ORNL Liquid Low-Level Waste Solidification

Description: The solidification of LLLW at ORNL has developed two basic strategies, a near-term or backup flowsheet is planned to alleviate the immediate capacity problem for storage of concentrated LLLW and a long-term or reference flowsheet is planned to incorporate filtration of the settleable TRU and cesium and strontium decontamination of the LLLW. Presently a feasibility study is evaluating the process alternatives for segregating LLLW from remote-handled transuranic (RH-TRU) sludges, decontamination … more
Date: January 1, 1987
Creator: Schultz, R. M.; Monk, T. H.; du Mont, S. P.; Helms, R. E.; Keigan, M. V. & Morris, M. I.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

ORNL PWR Blowdown Heat Transfer Program

Description: The PWR-Blowdown Heat Transfer Program is an experimental, separate effects, study of the relations among the principal variables that can alter the rate of blowdown, the presence of flow reversal and re-reversal, and time delay to critical heat flux, the rate at which dryout progresses, and similar time- related functions that are important to LOCA analysis. Primary test results will be obtained from the Thermal Hydraulic Test Facility (THTF), a large, non-nuclear pressurized-water loop which … more
Date: January 1, 1975
Creator: Thomas, D. G.; Bennett, R. F.; Hedrick, R. A.; Sheppard, J. D.; Eads, B. G.; Helms, R. E. et al.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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