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Intermediate Heat Exchanger Preliminary Design. Vol. 1, IHX Preliminary Design

Description: Preface: The intermediate heat exchanger is designed for operation in a nuclear power plant using liquid sodium as the primary and secondary coolant. Since the primary fluid coming from the reactor is radioactive, the purpose of the IHX is to transfer heat to a nonradioactive fluid which then goes to a steam generator. Because of this activity the until will be enclosed in a concrete pit and will not be accessible during periods of operation. Immediately after shut down it will be necessary … more
Date: February 28, 1959
Creator: Alco Products (Firm)
Item Type: Refine your search to only Report
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A Miniature Mixer Settler

Description: Unit developed at Knolls Atomic Power Laboratory for extraction and overcomes the disadvantages of the batch countercurrent units currently in use.
Date: January 5, 1956
Creator: Alter, H. Ward; Coplan, B. V. & Zebroski, E. L.
Item Type: Refine your search to only Report
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Uranium Concentration Meter

Description: From abstract; "Two basic instruments were developed for determining the concentration of uranium in solutions. Both instruments detect the gamma activity present in a sample solution, and interpret this analysis into direct presentation as parts per million."
Date: September 24, 1956
Creator: Arnett, Orville
Item Type: Refine your search to only Report
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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
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Plant Transient Analysis of the APPR-1 by Analog Computer Methods ; Task No. IV

Description: Phase I - Plant Transient Analysis. Behavior of the basic and refined kinetic models differs only slightly. It is therefore suggested that the basic model be used in any studies where the improvement in fidelity attainable fro the refined model is not warranted by the complexities introduced by the addition of function generator to the analog circuitry and derivation of the function to be programmed. The parameter responses of both kinetic models appear to be essentially similar to those of t… more
Date: October 1, 1958
Creator: Brondel, J. O. & Tomonto, J. R.
Item Type: Refine your search to only Report
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SM-1 (APPR-1) Research and Development Program : Final Report on Short-Lived and Fission Product Activity in the SM-1 Primary Coolant, Task III

Description: Abstract: The primary coolant of the SM-1 (APPR-1) was analyzed for short-lived and fission product activities. Manganese-56 was found to be the predominant non-fission product nuclide contributing to the short lived activity. Fission products were found in the coolant. It is concluded these fission products originate from a defects in the cladding and from surface contamination of the fuel elements.
Date: March 10, 1959
Creator: Brown, William S. & Hasse, Robert A.
Item Type: Refine your search to only Report
open access

SM-1 Research and Development Program, Activity Buildup Program Task 1 : final report February 1958 to June 1959

Description: Abstract: The results of activity buildup studies in the SM-1 (APPR-1) performed from February 1958 to January 1959 are reported. Data are presented on the extent, nature, and mechanism of the buildup of long-lived gamma emitting nuclides in the reactor primary system. Mathematical equations to describe the activity buildup are derived. Radiation levels after reactor shutdown are presented, as well as the predicted radiation levels at the end of core life.
Date: August 10, 1959
Creator: Brown, William S.; Bergen, C. Richard.; Bergmann, Carl A.; Chupak, Julius.; Fitzsimmons, Susanne R. & Grant, Louis G.
Item Type: Refine your search to only Report
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