A new fuel modeling capability, CTFFuel, with a case study on the fuel thermal conductivity degradation

doi:10.1016/j.nucengdes.2018.11.010

Title: A new fuel modeling capability, CTFFuel, with a case study on the fuel thermal conductivity degradation

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Abstract

Here, a new fuel modeling capability, CTFFuel, is developed from the subchannel code, CTF. This code is a standalone interface to the CTF fuel rod models, allowing for fuel rod simulations to be run independently from the fluid. This paper provides an overview of the code with a case study on the thermal conductivity degradation of LWR fuels to demonstrate its capabilities. The modeling of fuel thermal conductivity degradation in the code is improved through the addition of new modeling options to account for the irradiation effects via globally defined parameters. After the initial implementation, a variety of order-of-accuracy tests and code comparisons are performed to test software quality. A controlled analysis is allowed by CTFFuel to verify the numerical scheme of CTF’s conduction solution and to benchmark its fuel temperature predictions against FRAPCON-4.0’s. Overall, the software quality and verification procedure ensures that the new model is coded correctly, that it properly interacts with the rest of the code.

Authors:

Toptan, Aysenur ^[1];

^[2]; Avramova, Maria N. ^[1];

^[2]; Kropaczek, David J. ^[3]

North Carolina State Univ., Raleigh, NC (United States)
Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
North Carolina State Univ., Raleigh, NC (United States); Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)

Publication Date:: 2018-11-19

Research Org.:: Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)

Sponsoring Org.:: USDOE

OSTI Identifier:: 1489593

Grant/Contract Number:: AC05-00OR22725

Resource Type:: Accepted Manuscript

Journal Name:: Nuclear Engineering and Design

Additional Journal Information:: Journal Volume: 341; Journal Issue: C; Journal ID: ISSN 0029-5493

Publisher:: Elsevier

Country of Publication:: United States

Language:: English

Subject:: 11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS; CTFFuel; Thermal conductivity degradation; CTF; SQA; Verification

Citation Formats


                    Toptan, Aysenur, Salko, Robert K., Avramova, Maria N., Clarno, Kevin T., and Kropaczek, David J. A new fuel modeling capability, CTFFuel, with a case study on the fuel thermal conductivity degradation.  United States: N. p., 2018. 
        Web.  doi:10.1016/j.nucengdes.2018.11.010.

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                    Toptan, Aysenur, Salko, Robert K., Avramova, Maria N., Clarno, Kevin T., & Kropaczek, David J. A new fuel modeling capability, CTFFuel, with a case study on the fuel thermal conductivity degradation.  United States.  doi:10.1016/j.nucengdes.2018.11.010.

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                    Toptan, Aysenur, Salko, Robert K., Avramova, Maria N., Clarno, Kevin T., and Kropaczek, David J. Mon .  
        "A new fuel modeling capability, CTFFuel, with a case study on the fuel thermal conductivity degradation".  United States.  doi:10.1016/j.nucengdes.2018.11.010.  https://www.osti.gov/servlets/purl/1489593.

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@article{osti_1489593,

  title        = {A new fuel modeling capability, CTFFuel, with a case study on the fuel thermal conductivity degradation},

  author       = {Toptan, Aysenur and Salko, Robert K. and Avramova, Maria N. and Clarno, Kevin T. and Kropaczek, David J.},

  abstractNote = {Here, a new fuel modeling capability, CTFFuel, is developed from the subchannel code, CTF. This code is a standalone interface to the CTF fuel rod models, allowing for fuel rod simulations to be run independently from the fluid. This paper provides an overview of the code with a case study on the thermal conductivity degradation of LWR fuels to demonstrate its capabilities. The modeling of fuel thermal conductivity degradation in the code is improved through the addition of new modeling options to account for the irradiation effects via globally defined parameters. After the initial implementation, a variety of order-of-accuracy tests and code comparisons are performed to test software quality. A controlled analysis is allowed by CTFFuel to verify the numerical scheme of CTF’s conduction solution and to benchmark its fuel temperature predictions against FRAPCON-4.0’s. Overall, the software quality and verification procedure ensures that the new model is coded correctly, that it properly interacts with the rest of the code.},

  doi          = {10.1016/j.nucengdes.2018.11.010},

  journal      = {Nuclear Engineering and Design},

  number       = C,

  volume       = 341,

  place        = {United States},

  year         = {2018},

  month        = {11}

}

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DOI: 10.1016/j.nucengdes.2018.11.010

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