33
Views
5
CrossRef citations to date
0
Altmetric
Technical Paper

Interchannel Mixing in Wire Wrapped Liquid Metal Fast Reactor Fuel Assemblies

&
Pages 36-52 | Published online: 10 May 2017

References

  • N. E. TODREAS and L. W. WILSON, “Coolant Mixing in Sodium Cooled Fast Reactor Fuel Bundles,” WASH-1096, U.S. Atomic Energy Commission (April 1968).
  • T. R. BUMP, “Coolant Mixing in Fuel Subassemblies,” Trans. Am. Nucl. Soc., 9, 285 (1966).
  • W. BAUMANN, H. HOFFMAN, and K. RUST, “Auswahl von Abstand shaltern fur die Brennelemente Schneller Brutreaktoren,” Proc. International Meeting on Fast Reactor Fuel and Fuel Elements, Karlsruhe, September 1970.
  • Y. OKAMOTO, M. HISHIDA, and N. AKINO, “Hydraulic Performance in Rod-Bundles of Fast Reactor Fuels—Pressure Drop, Vibration and Mixing Coefficient,” Proc. Symp. Progress in Sodium-Cooled Fast Reactor Engineering, Monaco, IAEA/SM-130/5, International Atomic Energy Agency (March 1970).
  • J. SKOK, unpublished data, to G. Denielou, Centre d’Etudes Nucleaires de Cadarache, France, Personal Communication (July 1970).
  • R. A. CUSHMAN, “Subchannel Coolant Mixing and Temperature Analysis in EBR-II Instrumented Subassembly XX01,” Trans. Am. Nucl. Soc., 14, 1, 250 (1971).
  • M. K. MILLHOLLEN and A. M. SUTEY, “PNL-17. EBR-II Instrumented Subassembly Test Interim Report,” BNWL-1424, Battelle-Northwest Laboratories (June 1970).
  • J. HOWIESON and G. D. McPHERSON, “Coolant Mixing in 19-Element Fuel Bundles,” TDSI-31, Atomic Energy of Canada Limited (July 1961).
  • G. J. CLARKE, “Mixing Studies of Types C19C15A and C19C15B Fuel Bundles,” TDVI-15, Atomic Energy of Canada Limited (October 1960).
  • T. T. SHIMAZAKI and W. J. FREEDE, “Heat Transfer and Hydraulic Characteristics of the SRE Fuel Element,” Reactor Heat Transfer Conference of 1956, TID-7529, Part I, Book 1, U.S. Atomic Energy Commission (1957).
  • E. D. WATERS, “Fluid Mixing Experiments with a Wire Wrapped 7-Rod Bundle Fuel Assembly,” HW-70178 (Rev. November 1963), Hanford Laboratories (August 1963).
  • A. A. BISHOP, P. A. NELSON, and E. A. McCAFE, Jr., “Thermal and Hydraulic Design of the CVTR Fuel Assemblies,” CVNA-115, Westinghouse (June 1962).
  • E. ARANOVITCH and J. REYEN, “Mixing Experiments,” EUR-1830e, Part III, USAEC/Euratom Exchange Program (1964).
  • R. NIJSESIG and W. EIFLER, Nucl. Eng. Des., 4, 253 (1966).
  • R. NIJSmG, I. GARGANTDSII and W. EIFLER, Nucl. Eng. Des., 4, 375 (1966).
  • L. D. FELTEN, R. B. CASSIDY, and J. W. DODD, “HWOCR Multichannel Cross Flow Studies,” AI-CE-1089, Atomics International (November 1966).
  • G. MENZEL and J. H. BRESIDLEY, “Coolant Mixing Tests for 37-Rod, HWOCR-Type Fuel Bundles,” AI-CE-MEMO-61, Atomics International (June 1967).
  • R. D. COLLINS and J. FRANCE, “Mixing of Coolant in Channels Between Close Packed Fuel Elements,” IGR-TM/CA-847, U.K. Atomic Energy Agency (January 1958).
  • J. TURI, “An Investigation of Interchannel Mixing in Wire Wrapped Liquid Metal Fast Breeder Reactor Fuel Assemblies,” MS Thesis, Massachusetts Institute of Technology (September 1970).
  • V. R. MARIAN and D. P. HINES, “Transfer of Coolant Between Adjacent Subchannels in Wire Wrap Spacer and Grid Spacer Bundles,” Trans. Am. Nucl. Soc., 13, 807 (1970).
  • C. L. WHEELER, G. C. MAIN, and D. C. KOLESAR, “COBRA II A: A Program for Thermal-Hydraulie Analysis in Very Large Bundles of Fuel Pins,” BNWL-1422, Battelle-Northwest Laboratories (August 1970).
  • J. T. ROGERS and W. R. TARASUK, “Natural Mixing of Coolant in Close-Packed Nuclear Reactor Fuel Bundles,” Proc. Canadian Congress of Applied Mechanics (May 1967); also, R64CAP 29-1, Canadian General Electric (July 1966).
  • D. S. ROWE, “COBRA-II: A Digital Computer Program for Thermal-Hydraulic Subchannel Analysis of Rod Bundle Nuclear Fuel Elements,” BNWL-1229, Battelle-Northwest Laboratories (February 1970).
  • D. S. ROWE and C. W. ANGLE, “Crossflow Mixing Between Parallel Flow Channels During Boiling, Part II. Measurement of Flow and Enthalpy in Two Parallel Channels,” BNWL-371, Part II, Battelle-Northwest Laboratories (December 1967).
  • J. T. ROGERS and N. E. TODREAS, “Coolant Interchannel Mixing in Reactor Fuel Rod Bundles, Single-Phase Coolants,” in Symposium Volume, Heat Transfer in Rod Bundles, ASME Winter Meeting (1968).
  • J. T. ROGERS and W. R. TARASUK, “Coolant Mixing in Reactor Fuel Bundles. Part II. Forced Mixing by Flow Sweeping, R68-CAP32, Canadian General Electric (September 1968).
  • R. G. ROSEHART and J. T. ROGERS, “Turbulent Interchange Mixing Between Subchannels in Close-Packed Nuclear Reactor Fuel Bundles, Part I—Single Phase Coolant Generalized Correlation, R69PP1, Atomic Energy of Canada Limited (February 1969).

Reprints and Corporate Permissions

Please note: Selecting permissions does not provide access to the full text of the article, please see our help page How do I view content?

To request a reprint or corporate permissions for this article, please click on the relevant link below:

Academic Permissions

Please note: Selecting permissions does not provide access to the full text of the article, please see our help page How do I view content?

Obtain permissions instantly via Rightslink by clicking on the button below:

If you are unable to obtain permissions via Rightslink, please complete and submit this Permissions form. For more information, please visit our Permissions help page.