SM-2 Full Scale Flow Studies Termination Report

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Abstract: Hydrodynamic flow studies were conducted on a full scale model of the SM-2 reactor vessel and core. Test fluid was water at 200 psi and 200 degree F. Test facilities, model, and instrumentation design are discussed. Flow distribution in the stationary fuel elements, lattices, and control rods of the second pass was investigated. Pressure losses through the various core components were measured and are compared with calculated values. Observed over-all pressure drop was 71 feet of water at 200 degree F, 31% higher than predicted, part of which was due to presence of instrument leads. Element to element flow … continued below

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xxi, 198 pages.

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Christenson, J. A.; Richards, W. M. S. & Davidson, S. L. July 30, 1961.

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Abstract: Hydrodynamic flow studies were conducted on a full scale model of the SM-2 reactor vessel and core. Test fluid was water at 200 psi and 200 degree F. Test facilities, model, and instrumentation design are discussed. Flow distribution in the stationary fuel elements, lattices, and control rods of the second pass was investigated. Pressure losses through the various core components were measured and are compared with calculated values. Observed over-all pressure drop was 71 feet of water at 200 degree F, 31% higher than predicted, part of which was due to presence of instrument leads. Element to element flow distribution varied approximately +-8% from pass average. Channel-to-channel stationary element flow distribution varied approximately +-10% from element average and control rod flow distribution varied from +-8.9% to +-6.4 and -11.6% depending upon rod locations. These variations exceed the original goals of a +-10% and +-12% combined deviation for stationary and control rod elements respectively, but are satisfactory in relation to thermal design. There was no indication of unsatisfactory structural performance of any components under hydrodynamic loadings up to 130% of design values. The test program was terminated after determining flow distribution in the reference core design, omitting any work on the less critical first pass. Based on present understanding of the causes for the observed non-uniformity in distribution, achievement of the target tolerances throughout the reactor should be possible if the test program is to be continued. Recommendations for some of the modifications are contained in this report.

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xxi, 198 pages.

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Digitized from microopaque cards.

Contract No. AT(30-3)-326 with the U.S. Atomic Energy Commission, New York Operations Office.

Includes bibliographic references (page 171)

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  • Report No.: APAE-89
  • Grant Number: AT(30-3)-326
  • SuDoc Number: Y 3.AT 7:22/APAE-89
  • Accession or Local Control No: metadc1201985
  • Archival Resource Key: ark:/67531/metadc1201985

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  • July 30, 1961

Added to The UNT Digital Library

  • Aug. 15, 2019, 10:26 p.m.

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  • March 20, 2023, 5:48 p.m.

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Christenson, J. A.; Richards, W. M. S. & Davidson, S. L. SM-2 Full Scale Flow Studies Termination Report, report, July 30, 1961; Schenectady, New York.. (https://digital.library.unt.edu/ark:/67531/metadc1201985/: accessed June 22, 2025), University of North Texas Libraries, UNT Digital Library, https://digital.library.unt.edu; crediting UNT Libraries Government Documents Department.

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