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Nuclear Technology Volume 46, 1979 - Issue 2: Nuclear Power Reactor Safety (Presented at the ENS/ANS International Meeting, Brussels, Belgium, October 16-19, 1978) Part One
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Technical Paper

A New Approach for Rod-Bundle Thermal-Hydraulic Analysis

W. T. ShaArgonne National Laboratory, 9700 South Cass Avenue, Argonne, Illinois 60439
,
H. M. DomanusArgonne National Laboratory, 9700 South Cass Avenue, Argonne, Illinois 60439
,
R. C. SchmittArgonne National Laboratory, 9700 South Cass Avenue, Argonne, Illinois 60439
,
J. J. OrasArgonne National Laboratory, 9700 South Cass Avenue, Argonne, Illinois 60439
,
E. I. H. LinArgonne National Laboratory, 9700 South Cass Avenue, Argonne, Illinois 60439
&
V. L. ShahArgonne National Laboratory, 9700 South Cass Avenue, Argonne, Illinois 60439
Pages 268-280 | Published online: 10 May 2017

References

  • W. T. SHA, R. C. SCHMITT, and E. I. H. LIN, “THI3D-1: A Computer Program for Steady-State Thermal-Hydraulic Multichannel Analysis,” ANL-77-15, Argonne National Laboratory (July 1977).
  • D. S. ROWE, “COBRA-IIIC: A Digit Computer Program for Steady-State and Transient Thermal-Hydraulic Analysis of Rod Bundle Nuclear Fuel Elements,” BNWL-1695, Battelle-Pacific Northwest Laboratories (Mar. 1973).
  • R. POTTER et al., “SABRE 1: A Computer Program for the Calculation of Three-Dimensional Flows in Rod Clusters,” AEWW-R 1057 (July 1976).
  • W. T. SHA, H. M. DOMANUS, R. C. SCHMITT, J. J. ORAS, and E. I. H. LIN, “COMMIX-1: A Three-Dimensional, Transient, Single-Phase Component Computer Program for Thermal-Hydraulic Analysis,” NUREG-0415, ANL-77-96, Argonne National Laboratory (Jan. 1978).
  • W. J. WNEK, J. D. RAMSHAW, J. A. TRAPP, E. D. HUGHES, and C. W. SOLBRIG, “Transient Three-Dimensional Thermal-Hydraulic Analysis of Nuclear Reactor Fuel Rod Arrays: General Equations and Numerical Scheme,” ANCR-1207, Aerojet Nuclear Company (Nov. 1975).
  • M. H. FONTANA, R. E. MacPHERSON, P. A. GNADT, L. F. PARSLY, and J. L. WANTLAND, “Temperature Distribution in a 19-Rod Simulated LMFBR Fuel Assembly in a Hexagonal Duct (Fuel Failure Mockup Bundle 2A)-Record of Experimental Data,” ORNL-TM-4113, Oak Ridge National Laboratory (Sep. 1973).
  • H. M. DOMANUS and W. T. SHA, “Three-Dimensional Numerical Simulation of Flow Blockage in a 19-Pin LMFBR Fuel Assembly,” Trans. Am. Nucl. Soc., 30, 534 (1978).
  • M. H. FONTANA, P. A. GNADT, T. S. KRESS, R. E. MacPHERSON, L. F. PARSLY, and J. L. WANTLAND, “Temperature Distribution in 19-Rod Simulated LMFBR Fuel Assemblies With and Without an Edge Blockage (Out-of-Reactor Tests for ANL SLSF PI Experiment)-Record of Experimental Data for Fuel Failure Mockup Bundles 5B and 5C,” ORNL-TM-5003, Oak Ridge National Laboratory (Jan. 1976).
  • H. M. DOMANUS, R. C. SCHMITT, and W. T. SHA, “Numerical Results Obtained from the Three-Dimensional, Transient, Single-Phase Version of the COMMIX Computer Code,” NUREG-0355, ANL-CT-78-3, Argonne National Laboratory (Oct. 1977).

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