Analysis of multiple-tube ruptures in both steam generators for the Three Mile Island-1 pressurized water reactor

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The operator guidelines were followed for both transients described. Both transients resulted in SG overfill and the tube-rupture flow did not terminate in either transient. The following statements can be deducted from the results of the calculations: the tube-rupture flow could not be stopped for either case during 2600 s (43 min) of transient time; each accident scenario resulted in SG overfill; both SGs overfilled by 1600 s (27 min) and 1800 s (30 min) for Cases 1 and 2, respectively; conditions for isolation of the SGs were not reached; and core subcooling was not lost in either case but ... continued below

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Pages: 30

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Nassersharif, B. January 1, 1985.

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Description

The operator guidelines were followed for both transients described. Both transients resulted in SG overfill and the tube-rupture flow did not terminate in either transient. The following statements can be deducted from the results of the calculations: the tube-rupture flow could not be stopped for either case during 2600 s (43 min) of transient time; each accident scenario resulted in SG overfill; both SGs overfilled by 1600 s (27 min) and 1800 s (30 min) for Cases 1 and 2, respectively; conditions for isolation of the SGs were not reached; and core subcooling was not lost in either case but the upper head was voided in Case 2. Comparison of the cooldown rates in the two cases after 1200 s (20 min) shows that these rates are equal (i.e., restart of the RCPs did not change the primary-system cooldown rate). However, in Case 2, a steam bubble was formed in the upper head, which did not disappear during the simulated time. One of the immediate actions in the guidelines was to fill both SGs to 95% level. This step was almost unnecessary because the tube-rupture flow was large enough that the 15.4 - mK/s (100 - /sup 0/F h) cooldown-rate limit was exceeded and AFW could not be injected. Also, the guidelines did not address the SG overfill issue.

Physical Description

Pages: 30

Notes

NTIS, PC A03/MF A01 - GPO.

Source

  • 3. international meeting on reactor thermal hydraulics, Newport, RI, USA, 15 Oct 1985

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  • Other: TI85010105
  • Report No.: LA-UR-85-946
  • Report No.: CONF-851007-6
  • Grant Number: W-7405-ENG-36
  • Office of Scientific & Technical Information Report Number: 5040153
  • Archival Resource Key: ark:/67531/metadc1059106

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Office of Scientific & Technical Information Technical Reports

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  • January 1, 1985

Added to The UNT Digital Library

  • Jan. 22, 2018, 7:23 a.m.

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  • Feb. 1, 2018, 6:58 p.m.

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Nassersharif, B. Analysis of multiple-tube ruptures in both steam generators for the Three Mile Island-1 pressurized water reactor, article, January 1, 1985; New Mexico. (digital.library.unt.edu/ark:/67531/metadc1059106/: accessed June 21, 2018), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.