Study on hydrodynamically induced dryout and post dryout important to heavy water reactors

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Description

Recently, the safety of low pressure liquid cooled nuclear reactors has become a very important issue with reference to the operation of the heavy water reactors at Savannah River Plant. Under accident conditions such as loss-of-flow or loss-of-coolant, these reactors typically encounter unstable two-phase flow which may lead to the occurrence of dryout and subsequent fuel failure. An analytical study using the one-dimensional drift flux model was carried out to investigate the two-phase flow instability for Westinghouse Savannah River Site reactor. The analysis indicates that the first and higher order instabilities exist in the possible transient operational conditions. The instabilities ... continued below

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Medium: P; Size: 127 p.

Creation Information

Ishii, M.; Revankar, S.T.; Nair, S.; Lele, S.; Eberle, C.S. & Babelli, I. January 1, 1995.

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Description

Recently, the safety of low pressure liquid cooled nuclear reactors has become a very important issue with reference to the operation of the heavy water reactors at Savannah River Plant. Under accident conditions such as loss-of-flow or loss-of-coolant, these reactors typically encounter unstable two-phase flow which may lead to the occurrence of dryout and subsequent fuel failure. An analytical study using the one-dimensional drift flux model was carried out to investigate the two-phase flow instability for Westinghouse Savannah River Site reactor. The analysis indicates that the first and higher order instabilities exist in the possible transient operational conditions. The instabilities are encountered at higher heat fluxes or lower flow rates. The subcooling has a stabilizing effect except at very low subcooling. An experimental loop has been designed and constructed. A study was conducted on the CHF induced by various flow instabilities. Details of this test loop are presented.

Physical Description

Medium: P; Size: 127 p.

Notes

INIS; OSTI as DE95008642

Source

  • Other Information: PBD: Jan 1995

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  • Other: DE95008642
  • Report No.: DOE/ER/13045--T2
  • Report No.: PU-NE--95/1
  • Grant Number: FG02-90ER13045
  • DOI: 10.2172/36660 | External Link
  • Office of Scientific & Technical Information Report Number: 36660
  • Archival Resource Key: ark:/67531/metadc679569

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  • January 1, 1995

Added to The UNT Digital Library

  • July 25, 2015, 2:20 a.m.

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  • Nov. 25, 2015, 4:12 p.m.

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Ishii, M.; Revankar, S.T.; Nair, S.; Lele, S.; Eberle, C.S. & Babelli, I. Study on hydrodynamically induced dryout and post dryout important to heavy water reactors, report, January 1, 1995; United States. (digital.library.unt.edu/ark:/67531/metadc679569/: accessed September 23, 2017), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.