A Study of Complete Loss of Coolant Flow in the Yankee Reactor

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The complete loss of primary coolant flow accident caused by the instantaneous loss of power to all four pumps was investigated. The principal objective was to determine the elapsed time from the initiation of the pump failure to the occurrence of bulk boiling at the outlet of the hot channel. Inherent was the determination of operating conditions necessary to eliminate the hot channel bulk boiling, these being added inertia in the primary coolant loop and scram delay time. Both the 392 Mw core and the 482 Mw core were included in the investogation. The results show that additional inertia is ... continued below

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Pages: 112

Creation Information

Gallagher, J. M., Jr. & Hunter, D. November 1, 1958.

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Description

The complete loss of primary coolant flow accident caused by the instantaneous loss of power to all four pumps was investigated. The principal objective was to determine the elapsed time from the initiation of the pump failure to the occurrence of bulk boiling at the outlet of the hot channel. Inherent was the determination of operating conditions necessary to eliminate the hot channel bulk boiling, these being added inertia in the primary coolant loop and scram delay time. Both the 392 Mw core and the 482 Mw core were included in the investogation. The results show that additional inertia is required as well as scram if bulk boiling is to be eliminated. As a result of several of the assumptions made, the investigation was limited to a study of that region of the reactor core where heat transfer takes place between the fuel and the coolant; primary system components such as the pressurizer and steam generator were excluded. The film heat transfer coefficient was varied as a function of flow rate but not as a function of coolant temperature, thus boiling phenomena were not included. Distributed parameter effects were incorporated in equations which describe the core thermal kinetics by an approximation technique. An approximation technique is also presented which allows the extrapolation of the results to the two pump failure case. Data for the investigation were obtained by the use of a general purpose d-c analog computer. (auth)

Physical Description

Pages: 112

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Source

  • Other Information: For Yankee Atomic Electric Co. Orig. Receipt Date: 31-DEC-59

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  • Report No.: YAEC-83
  • Grant Number: AT(30-3)-222, SUBCONTRACT NO. 1
  • DOI: 10.2172/4303202 | External Link
  • Office of Scientific & Technical Information Report Number: 4303202
  • Archival Resource Key: ark:/67531/metadc1024715

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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.

Office of Scientific and Technical Information (OSTI) is the Department of Energy (DOE) office that collects, preserves, and disseminates DOE-sponsored research and development (R&D) results that are the outcomes of R&D projects or other funded activities at DOE labs and facilities nationwide and grantees at universities and other institutions.

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Creation Date

  • November 1, 1958

Added to The UNT Digital Library

  • Oct. 15, 2017, 10:09 p.m.

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  • Jan. 17, 2018, 2:57 p.m.

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Gallagher, J. M., Jr. & Hunter, D. A Study of Complete Loss of Coolant Flow in the Yankee Reactor, report, November 1, 1958; Pittsburgh, Pennsylvania. (digital.library.unt.edu/ark:/67531/metadc1024715/: accessed July 22, 2018), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.