Thermal-hydraulic instabilities in pressure tube graphite-moderated boiling water reactors

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Thermally induced two-phase instabilities in non-uniformly heated boiling charmers in RBMK-1000 reactor have been analyzed using RELAP5/MOD3 code. The RELAP5 model of a RBMK-1000 reactor was developed to investigate low flow in a distribution group header (DGH) supplying 44 fuel pressure tubes. The model was evaluated against experimental data. The results of the calculations indicate that the period of oscillation for the high power tube varied from 3.1s to 2.6s, over the power range of 2.0 MW to 3.0 MW, respectively. The amplitude of the flow oscillation for the high powered tube varied from +100% to {minus}150% of the tube ... continued below

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9 p.

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Tsiklauri, G. & Schmitt, B. September 1, 1995.

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  • Pacific Northwest Laboratory
    Publisher Info: Pacific Northwest Lab., Richland, WA (United States)
    Place of Publication: Richland, Washington

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Description

Thermally induced two-phase instabilities in non-uniformly heated boiling charmers in RBMK-1000 reactor have been analyzed using RELAP5/MOD3 code. The RELAP5 model of a RBMK-1000 reactor was developed to investigate low flow in a distribution group header (DGH) supplying 44 fuel pressure tubes. The model was evaluated against experimental data. The results of the calculations indicate that the period of oscillation for the high power tube varied from 3.1s to 2.6s, over the power range of 2.0 MW to 3.0 MW, respectively. The amplitude of the flow oscillation for the high powered tube varied from +100% to {minus}150% of the tube average flow. Reverse flow did not occur in the lower power tubes. The amplitude of oscillation in the subcooled region at the inlet to the fuel region is higher than in the saturated region at the outlet. In the upper fuel region and outlet connectors the flow oscillations are dissipated. The threshold of flow instability for the high powered tubes of a RBMK reactor is compared to Japanese data and appears to be in good agreement.

Physical Description

9 p.

Notes

INIS; OSTI as DE96002469

Source

  • 7. international topical meeting on nuclear reactor thermal-hydraulics (Nureth-7), Saratoga Springs, NY (United States), 10-15 Sep 1995

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  • Other: DE96002469
  • Report No.: PNL-SA--26346
  • Report No.: CONF-950904--7
  • Grant Number: AC06-76RL01830
  • Office of Scientific & Technical Information Report Number: 183221
  • Archival Resource Key: ark:/67531/metadc669220

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Office of Scientific & Technical Information Technical Reports

Reports, articles and other documents harvested from the Office of Scientific and Technical Information.

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  • September 1, 1995

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  • June 29, 2015, 9:42 p.m.

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  • April 7, 2016, 6:13 p.m.

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Tsiklauri, G. & Schmitt, B. Thermal-hydraulic instabilities in pressure tube graphite-moderated boiling water reactors, article, September 1, 1995; Richland, Washington. (digital.library.unt.edu/ark:/67531/metadc669220/: accessed August 14, 2018), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.