Multiphysics simulation of VVER-1200 fuel performance during normal operating conditions

Khaled M. Yassin; Mohamed H. Hassan; Mohammad M. Ghoneim; Mostafa S. Elkolil; Adel Alyan; Said A. Agamy

doi:10.1007/s41365-023-01172-9

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Multiphysics simulation of VVER-1200 fuel performance during normal operating conditions

NUCLEAR ENERGY SCIENCE AND ENGINEERING | Updated：2023-03-20

- Multiphysics simulation of VVER-1200 fuel performance during normal operating conditions
- Nuclear Science and Techniques Vol. 34, Issue 2, Article number: 28(2023)
- Affiliations：
  
  1.Nuclear Research Center, Egyptian Atomic Energy Authority, Abo Zaabal, Cairo 13759, Egypt
  2.Department of Nuclear and Radiological Engineering, Faculty of Engineering, Alexandria University, Alexandria 21544, Egypt
  3.Faculty of Engineering, Egyptian Russian University, Badr 11829, Egypt
- Author bio：
  
  Khaled M. Yassin eng.khaled_m@yahoo.com
  Mohamed H. Hassan mohamed.hassan@alexu.edu.eg
  Mohammad M. Ghoneim mohghon1@yahoo.com
  Mostafa S. Elkolil moustafa_elkoliel@yahoo.com
  Adel Alyan adelalyan@yahoo.com
  Said A. Agamy sa_agamy@yahoo.com
- Funds：
- DOI：10.1007/s41365-023-01172-9
  CLC：
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Khaled M. Yassin, Mohamed H. Hassan, Mohammad M. Ghoneim, et al. Multiphysics simulation of VVER-1200 fuel performance during normal operating conditions. [J]. Nuclear Science and Techniques 34(2):28(2023)
DOI：

Khaled M. Yassin, Mohamed H. Hassan, Mohammad M. Ghoneim, et al. Multiphysics simulation of VVER-1200 fuel performance during normal operating conditions. [J]. Nuclear Science and Techniques 34(2):28(2023) DOI： 10.1007/s41365-023-01172-9.

摘要

Abstract

Nuclear fuel performance modeling and simulation are critical tasks for nuclear fuel design optimization and safety analysis under normal and transient conditions. Fuel performance is a complicated phenomenon that involves thermal, mechanical, and irradiation mechanisms and requires special multiphysics modules. In this study, a fuel performance model was developed using the COMSOL Multiphysics platform. The modeling was performed for a 2D axis-symmetric geometry of a UO,2, fuel pellet in the E110 clad for VVER-1200 fuel. The modeling considers all relevant phenomena, including heat generation and conduction, gap heat transfer, elastic strain, mechanical contact, thermal expansion, grain growth, densification, fission gas generation and release, fission product swelling, gap/plenum pressure, and cladding thermal and irradiation creep. The model was validated using a code-to-code evaluation of the fuel pellet centerline and surface temperatures in the case of constant power, in addition to validation of fission gas release (FGR) predictions. This prediction proved that the model could perform according to previously published VVER nuclear fuel performance parameters. A sensitivity study was also conducted to assess the effects of uncertainty on some of the model parameters. The model was then used to predict the VVER-1200 fuel performance parameters as a function of burnup, including the temperature profiles, gap width, fission gas release, and plenum pressure. A compilation of related material and thermomechanical models was conducted and included in the modeling to allow the user to investigate different material/performance models. Although the model was developed for normal operating conditions, it can be modified to include off-normal operating conditions.

关键词

Keywords

VVER-1200Fuel performanceCOMSOL codeZr-1%Nb claddingUO2 fuel rod

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