TY - JOUR
T1 - A layered 2D computational framework
T2 - Theory and applications to nuclear fuel behavior
AU - Gamble, K. A.
AU - Spencer, B. W.
AU - Hales, J. D.
AU - Knight, T. W.
AU - Roberts, E.
N1 - Funding Information:
This work was funded by the US Department of Energy. The manuscript has been authored by a contractor of the U.S. Government under Contract DE-AC07-05ID14517. Accordingly, the U.S. Government retains a non-exclusive, royalty free license to publish or reproduce the published form of this contribution, or allow others to do so, for U.S. Government purposes. The corresponding author also thanks the Employee Education Program (EEP) at the Idaho National Laboratory for providing the opportunity to pursue further education through the University of South Carolina. This research also made use of the resources of the High Performance Computing Center at Idaho National Laboratory, which is supported by the Office of Nuclear Energy of the U.S. Department of Energy and the Nuclear Science User Facilities under Contract No. DE-AC07-05ID14517.
Funding Information:
This work was funded by the US Department of Energy. The manuscript has been authored by a contractor of the U.S. Government under Contract DE-AC07-05ID14517. Accordingly, the U.S. Government retains a non-exclusive, royalty free license to publish or reproduce the published form of this contribution, or allow others to do so, for U.S. Government purposes. The corresponding author also thanks the Employee Education Program (EEP) at the Idaho National Laboratory for providing the opportunity to pursue further education through the University of South Carolina.
Funding Information:
This research also made use of the resources of the High Performance Computing Center at Idaho National Laboratory, which is supported by the Office of Nuclear Energy of the U.S. Department of Energy and the Nuclear Science User Facilities under Contract No. DE-AC07-05ID14517.
Publisher Copyright:
© 2022 Elsevier B.V.
PY - 2022/8/15
Y1 - 2022/8/15
N2 - Nuclear fuel performance computer codes have been developed over the last 50 years to analyze fuel behavior under various operating conditions. Traditionally, these codes have used quasi-two-dimensional (also commonly known as 1.5D) representations of the fuel rod, which model the rod using a set of one-dimensional axisymmetric models that represent the behavior at specific axial positions on the rod. Modern fuel performance codes have the ability to investigate full three-dimensional (3D) effects and couple to other physics-based codes for true multiphysics simulations. However, with increasing complexity comes increasing computational costs. Many phenomena of interest involve azimuthally-varying behavior that cannot be represented using the aforementioned quasi-two-dimensional approach, but do not require the use of a full 3D model. To efficiently address these problems, there is a need for a computational framework that provides a compromise between the quasi-two-dimensional and full 3D models. This paper presents a new quasi-three-dimensional approach that represents the fuel rod as a set of 2D planar models that represent the behavior of the fuel cross-section at various axial positions. Presented here are the theory behind the methodology, test cases to illustrate proper implementation, and practical applications of its use in the BISON fuel performance code for a variety of cases in nuclear fuel analysis, such as fuel fracture, axial fuel relocation, and cladding distension and oxidation.
AB - Nuclear fuel performance computer codes have been developed over the last 50 years to analyze fuel behavior under various operating conditions. Traditionally, these codes have used quasi-two-dimensional (also commonly known as 1.5D) representations of the fuel rod, which model the rod using a set of one-dimensional axisymmetric models that represent the behavior at specific axial positions on the rod. Modern fuel performance codes have the ability to investigate full three-dimensional (3D) effects and couple to other physics-based codes for true multiphysics simulations. However, with increasing complexity comes increasing computational costs. Many phenomena of interest involve azimuthally-varying behavior that cannot be represented using the aforementioned quasi-two-dimensional approach, but do not require the use of a full 3D model. To efficiently address these problems, there is a need for a computational framework that provides a compromise between the quasi-two-dimensional and full 3D models. This paper presents a new quasi-three-dimensional approach that represents the fuel rod as a set of 2D planar models that represent the behavior of the fuel cross-section at various axial positions. Presented here are the theory behind the methodology, test cases to illustrate proper implementation, and practical applications of its use in the BISON fuel performance code for a variety of cases in nuclear fuel analysis, such as fuel fracture, axial fuel relocation, and cladding distension and oxidation.
KW - BISON
KW - Finite element analysis
KW - Fuel performance
KW - Layered2D framework
UR - https://www.scopus.com/pages/publications/85132702755
UR - https://www.mendeley.com/catalogue/dc42764f-5847-34f7-bfba-31c241d42870/
U2 - 10.1016/j.nucengdes.2022.111847
DO - 10.1016/j.nucengdes.2022.111847
M3 - Article
AN - SCOPUS:85132702755
SN - 0029-5493
VL - 395
JO - Nuclear Engineering and Design
JF - Nuclear Engineering and Design
M1 - 111847
ER -