Thermal–mechanical stress analysis of pressurized water reactor pressure vessel with/without a preexisting crack under grid load following conditions

Mohanty, Subhasish; Soppet, William K.; Majumdar, Saurin; Natesan, Krishnamurti

doi:10.1016/j.nucengdes.2016.09.020

Title: Thermal–mechanical stress analysis of pressurized water reactor pressure vessel with/without a preexisting crack under grid load following conditions

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Abstract

In this paper, we present thermal-mechanical stress analysis of a pressurized water reactor pressure vessel and its hot-leg and cold-leg nozzles. Results are presented from thermal and thermal-mechanical stress analysis under reactor heat-up, cool-down, and grid load-following conditions. Analysis results are given with and without the presence of preexisting crack in the reactor nozzle (axial crack in hot leg nozzle). From the model results it is found that the stress-strain states are significantly higher in case of presence of crack than without crack. In conclusion, the stress-strain state under grid load following condition are more realistic compared to the stress-strain state estimated assuming simplified transients.

Authors:

Mohanty, Subhasish ^[1]; Soppet, William K. ^[1]; Majumdar, Saurin ^[1]; Natesan, Krishnamurti ^[1]

Argonne National Lab. (ANL), Argonne, IL (United States)

Publication Date:: Wed Oct 26 00:00:00 EDT 2016

Research Org.:: Argonne National Lab. (ANL), Argonne, IL (United States)

Sponsoring Org.:: USDOE Office of Nuclear Energy (NE), Nuclear Reactor Technologies (NE-7), Light Water Reactor Sustainability Program; USDOE

OSTI Identifier:: 1391932

Alternate Identifier(s):: OSTI ID: 1397906

Grant/Contract Number:: AC02-06CH11357

Resource Type:: Accepted Manuscript

Journal Name:: Nuclear Engineering and Design

Additional Journal Information:: Journal Volume: 310; Journal Issue: C; Journal ID: ISSN 0029-5493

Publisher:: Elsevier

Country of Publication:: United States

Language:: English

Subject:: 42 ENGINEERING; 21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; FEM; Finite Element Method; Grid Load Following; Pressure Vessel; Pressurized Water Reactor; Stress Analysis; Thermal Analysis; Thermal-Mechanical Stress Analysis

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                    Mohanty, Subhasish, Soppet, William K., Majumdar, Saurin, and Natesan, Krishnamurti. Thermal–mechanical stress analysis of pressurized water reactor pressure vessel with/without a preexisting crack under grid load following conditions.  United States: N. p., 2016. 
Web.  doi:10.1016/j.nucengdes.2016.09.020.

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                    Mohanty, Subhasish, Soppet, William K., Majumdar, Saurin, & Natesan, Krishnamurti. Thermal–mechanical stress analysis of pressurized water reactor pressure vessel with/without a preexisting crack under grid load following conditions.  United States.  https://doi.org/10.1016/j.nucengdes.2016.09.020

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                    Mohanty, Subhasish, Soppet, William K., Majumdar, Saurin, and Natesan, Krishnamurti. Wed .  
"Thermal–mechanical stress analysis of pressurized water reactor pressure vessel with/without a preexisting crack under grid load following conditions".  United States.  https://doi.org/10.1016/j.nucengdes.2016.09.020.  https://www.osti.gov/servlets/purl/1391932.

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@article{osti_1391932,

  title        = {Thermal–mechanical stress analysis of pressurized water reactor pressure vessel with/without a preexisting crack under grid load following conditions},

  author       = {Mohanty, Subhasish and Soppet, William K. and Majumdar, Saurin and Natesan, Krishnamurti},

  abstractNote = {In this paper, we present thermal-mechanical stress analysis of a pressurized water reactor pressure vessel and its hot-leg and cold-leg nozzles. Results are presented from thermal and thermal-mechanical stress analysis under reactor heat-up, cool-down, and grid load-following conditions. Analysis results are given with and without the presence of preexisting crack in the reactor nozzle (axial crack in hot leg nozzle). From the model results it is found that the stress-strain states are significantly higher in case of presence of crack than without crack. In conclusion, the stress-strain state under grid load following condition are more realistic compared to the stress-strain state estimated assuming simplified transients.},

  doi          = {10.1016/j.nucengdes.2016.09.020},

  journal      = {Nuclear Engineering and Design},

  number       = C,

  volume       = 310,

  place        = {United States},

  year         = {Wed Oct 26 00:00:00 EDT 2016},

  month        = {Wed Oct 26 00:00:00 EDT 2016}

}

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