A layered 2D computational framework: Theory and applications to nuclear fuel behavior

Gamble, Kyle A.; Spencer, Benjamin W.; Hales, Jason D.; Knight, Travis W.; Roberts, Elwyn

doi:10.1016/j.nucengdes.2022.111847

A layered 2D computational framework: Theory and applications to nuclear fuel behavior

Journal Article · Tue Jun 21 00:00:00 EDT 2022 · Nuclear Engineering and Design

DOI:https://doi.org/10.1016/j.nucengdes.2022.111847· OSTI ID:1894948

^[1]; ^[2]; ^[2]; Knight, Travis W. ^[3]; Roberts, Elwyn ^[3]

Idaho National Lab. (INL), Idaho Falls, ID (United States); Univ. of South Carolina, Columbia, SC (United States)
Idaho National Lab. (INL), Idaho Falls, ID (United States)
Univ. of South Carolina, Columbia, SC (United States)

Nuclear fuel performance computer codes have been developed over the last 50 years to analyze fuel behavior under various operating conditions. Traditionally, these codes 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. In this paper, we present a new quasi-three-dimensional approach that represents the fuel 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.

View Accepted Manuscript (DOE)

Research Organization:: Idaho National Laboratory (INL), Idaho Falls, ID (United States)

Sponsoring Organization:: USDOE Office of Nuclear Energy (NE)

Grant/Contract Number:: AC07-05ID14517

OSTI ID:: 1894948

Alternate ID(s):: OSTI ID: 1961498

Report Number(s):: INL/JOU-21-63456-Rev000

Journal Information:: Nuclear Engineering and Design, Journal Name: Nuclear Engineering and Design Vol. 395; ISSN 0029-5493

Publisher:: ElsevierCopyright Statement

Country of Publication:: United States

Language:: English

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A layered 2D computational framework: Theory and applications to nuclear fuel behavior

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