Calculation of Savannah River K Reactor Mark-22 assembly LOCA/ECS power limits

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This paper summarizes the results of TRAC-PF1/MOD3 calculations of Mark-22 fuel assembly of loss-of-coolant accident/emergency cooling system (LOCA/ECS) power limits for the Savannah River Site (SRS) K Reactor. This effort was part of a larger effort undertaken by the Los Alamos National Laboratory for the US Department of Energy to perform confirmatory power limits calculations for the SRS K Reactor. A method using a detailed three-dimensional (3D) TRAC model of the Mark-22 fuel assembly was developed to compute LOCA/ECS power limits. Assembly power was limited to ensure that no point on the fuel assembly walls would exceed the local saturation ... continued below

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Pages: (28 p)

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Fischer, S.R.; Farman, R.F. & Birdsell, S.A. January 1, 1992.

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This paper summarizes the results of TRAC-PF1/MOD3 calculations of Mark-22 fuel assembly of loss-of-coolant accident/emergency cooling system (LOCA/ECS) power limits for the Savannah River Site (SRS) K Reactor. This effort was part of a larger effort undertaken by the Los Alamos National Laboratory for the US Department of Energy to perform confirmatory power limits calculations for the SRS K Reactor. A method using a detailed three-dimensional (3D) TRAC model of the Mark-22 fuel assembly was developed to compute LOCA/ECS power limits. Assembly power was limited to ensure that no point on the fuel assembly walls would exceed the local saturation temperature. The detailed TRAC model for the Mark-22 assembly consisted of three concentric 3D vessel components which simulated the two targets, two fuel tubes, and three main flow channels of the fuel assembly. The model included 100% eccentricity between the assembly annuli and a 20% power tilt. Eccentricity in the radial alignment of the assembly annuli arises because axial spacer ribs that run the length of the fuel and targets are used. Wall-shear, interfacial-shear, and wall heat-transfer correlations were developed and implemented in TRAC-PF1/MOD3 specifically for modeling flow and heat transfer in the narrow ribbed annuli encountered in the Mark-22 fuel assembly design. We established the validity of these new constitutive models using separate-effects benchmarks. TRAC system calculations of K Reactor indicated that the limiting ECS-phase accident is a double-ended guillonite break in a process water line at the pump discharge (i.e., a PDLOCA). The fuel assembly with the minimum cooling potential is identified from this system calculation. Detailed assembly calculations then were performed using appropriate boundary conditions obtained from this limiting system LOCA. Coolant flow rates and pressure boundary conditions were obtained from this system calculation and applied to the detailed assembly model.

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Pages: (28 p)

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OSTI; NTIS; INIS; GPO Dep.

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  • American Society of Mechanical Engineers national heat transfer conference and exposition, San Diego, CA (United States), 9-12 Aug 1992

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  • Other: DE92007434
  • Report No.: LA-UR-92-204
  • Report No.: CONF-920804--2
  • Grant Number: W-7405-ENG-36
  • Office of Scientific & Technical Information Report Number: 5210472
  • Archival Resource Key: ark:/67531/metadc1057676

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  • January 1, 1992

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  • Jan. 22, 2018, 7:23 a.m.

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  • Feb. 1, 2018, 7:01 p.m.

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Fischer, S.R.; Farman, R.F. & Birdsell, S.A. Calculation of Savannah River K Reactor Mark-22 assembly LOCA/ECS power limits, article, January 1, 1992; New Mexico. (digital.library.unt.edu/ark:/67531/metadc1057676/: accessed September 22, 2018), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.