Update to advanced neutron source steady-state thermal-hydraulic report

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Description

This report is intended to be a supplement to ORNL/TM-12398, Steady-State Thermal-Hydraulic Design Analysis of the Advanced Neutron Source Reactor. It updates the core thermal-hydrualic design to the latest three-element configuration and also provides the most recent information on the thermal-hydraulic statistical uncertainty analysis. In addition, it includes calculations of beam tube cooling and control rod lift forces, which were not addressed in the initial report. This report describes work that is a snapshot in time as it stood at the end of the project. The three-element core calculations include a description of changes made to the overall coolant system; ... continued below

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109 p.

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Yoder, G.L.; Carbajo, J.J.; Morris, D.G. & Nelson, W.R. May 1, 1996.

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Description

This report is intended to be a supplement to ORNL/TM-12398, Steady-State Thermal-Hydraulic Design Analysis of the Advanced Neutron Source Reactor. It updates the core thermal-hydrualic design to the latest three-element configuration and also provides the most recent information on the thermal-hydraulic statistical uncertainty analysis. In addition, it includes calculations of beam tube cooling and control rod lift forces, which were not addressed in the initial report. This report describes work that is a snapshot in time as it stood at the end of the project. The three-element core calculations include a description of changes made to the overall coolant system; however, most of the analysis is focused on fuel loading thermal-hydraulic calculations. This analysis uses updated uncertainty values and indicates that a two-dimensional fuel grading in the three-element core would still be necessary to meet the desired operating and safety criteria. Analysis of cooling in the reflector tank examines various cooling options for the reflector tank components. This work investigated multiple forced convection designs as well as natural convection cooling requirements. Lift forces on the inner control rods caused by the upward coolant flow were also examined. Initial control rod designs were such that a sheared control rod would tend to lift because of flow forces. Design changes were recommended that would eliminate this issue. They included geometry changes to the inner control rod cooling channels, changes to the orificing in the central hole region, and reduction of inner control rod coolant velocity.

Physical Description

109 p.

Notes

INIS; OSTI as DE96013253

Source

  • Other Information: PBD: May 1996

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  • Other: DE96013253
  • Report No.: ORNL/TM--12398/R1
  • Grant Number: AC05-96OR22464
  • DOI: 10.2172/283708 | External Link
  • Office of Scientific & Technical Information Report Number: 283708
  • Archival Resource Key: ark:/67531/metadc665007

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Office of Scientific & Technical Information Technical Reports

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  • May 1, 1996

Added to The UNT Digital Library

  • June 29, 2015, 9:42 p.m.

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  • Jan. 21, 2016, 1:30 p.m.

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Yoder, G.L.; Carbajo, J.J.; Morris, D.G. & Nelson, W.R. Update to advanced neutron source steady-state thermal-hydraulic report, report, May 1, 1996; Tennessee. (digital.library.unt.edu/ark:/67531/metadc665007/: accessed September 23, 2017), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.