Analysis of induced steam generator tube rupture using MAAP 4.0

Kenton, M; Epstein, M; Henry, R E; Paik, C; Fuller, E

Title: Analysis of induced steam generator tube rupture using MAAP 4.0

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Abstract

The nuclear industry has initiated a program of Steam Generator Degradation Specific Management (SGDSM) to cope with the various types of corrosion that have been observed in pressurized water reactor (PWR) steam generators. In parallel, the U.S. Nuclear Regulatory Commission is promulgating revised rules on steam generator tube integrity. To support these efforts, the Electric Power Research Institute has sponsored calculations with the MAAP 4 code. The principal objective of these calculations is to estimate the peak temperatures experienced by the steam generator tubes during high-pressure severe accidents. These results are used to evaluate the potential for degraded tubes to leak or rupture. Attention was focused on station blackout (SBO) accidents with loss of turbine-driven auxiliary feedwater because these generally result in the greatest threat to the tubes.

Authors:

Kenton, M ^[1]; Epstein, M; Henry, R E; Paik, C ^[2]; Fuller, E ^[3]

Dames & Moore, Westmont, IL (United States)
Fauske & Assoc., Inc., Burr Ridge, IL (United States)
Polestar Applied Technology, Los Altos, CA (United States)

Publication Date:: Tue Dec 31 00:00:00 EST 1996

OSTI Identifier:: 437029

Report Number(s):: CONF-9606116-
Journal ID: TANSAO; ISSN 0003-018X; TRN: 96:005275-0268

Resource Type:: Journal Article

Journal Name:: Transactions of the American Nuclear Society

Additional Journal Information:: Journal Volume: 74; Conference: Annual meeting of the American Nuclear Society (ANS), Reno, NV (United States), 16-20 Jun 1996; Other Information: PBD: 1996

Country of Publication:: United States

Language:: English

Subject:: 22 NUCLEAR REACTOR TECHNOLOGY; 99 MATHEMATICS, COMPUTERS, INFORMATION SCIENCE, MANAGEMENT, LAW, MISCELLANEOUS; 21 NUCLEAR POWER REACTORS AND ASSOCIATED PLANTS; PWR TYPE REACTORS; STEAM GENERATORS; REACTOR ACCIDENTS; M CODES; TUBES; RUPTURES; FEEDWATER; LEAKS

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                    Kenton, M, Epstein, M, Henry, R E, Paik, C, and Fuller, E. Analysis of induced steam generator tube rupture using MAAP 4.0.  United States: N. p., 1996. 
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                    Kenton, M, Epstein, M, Henry, R E, Paik, C, & Fuller, E. Analysis of induced steam generator tube rupture using MAAP 4.0.  United States.

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                    Kenton, M, Epstein, M, Henry, R E, Paik, C, and Fuller, E. 1996.  
        "Analysis of induced steam generator tube rupture using MAAP 4.0".  United States.

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@article{osti_437029,

  title        = {Analysis of induced steam generator tube rupture using MAAP 4.0},

  author       = {Kenton, M and Epstein, M and Henry, R E and Paik, C and Fuller, E},

  abstractNote = {The nuclear industry has initiated a program of Steam Generator Degradation Specific Management (SGDSM) to cope with the various types of corrosion that have been observed in pressurized water reactor (PWR) steam generators. In parallel, the U.S. Nuclear Regulatory Commission is promulgating revised rules on steam generator tube integrity. To support these efforts, the Electric Power Research Institute has sponsored calculations with the MAAP 4 code. The principal objective of these calculations is to estimate the peak temperatures experienced by the steam generator tubes during high-pressure severe accidents. These results are used to evaluate the potential for degraded tubes to leak or rupture. Attention was focused on station blackout (SBO) accidents with loss of turbine-driven auxiliary feedwater because these generally result in the greatest threat to the tubes.},

  doi          = {},

  url          = {https://www.osti.gov/biblio/437029},
  journal      = {Transactions of the American Nuclear Society},
number       = ,

  volume       = 74,

  place        = {United States},

  year         = {Tue Dec 31 00:00:00 EST 1996},

  month        = {Tue Dec 31 00:00:00 EST 1996}

}

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