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Approximate Multi-Objective Optimization of Gap Size of PWR Annular Nuclear Fuels

Jaehyeok Doh, Young Doo Kwon, Jongsoo Lee
JKSPE 2015;32(9):815-824.
Published online: September 1, 2015
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In this study, we conducted the approximate multi-objective optimization of gap sizes of pressurized-water reactor (PWR) annular fuels. To determine the contacting tendency of the inner-outer gaps between the annular fuel pellets and cladding, thermoelastic-plastic-creep (TEPC)analysis of PWR annular fuels was performed, using in-house FE code. For the efficient heat transfer at certain levels of stress, we investigated the tensile, compressive hoop stress and temperature, and optimized the gap sizes using the non-dominant sorting genetic algorithm (NSGA-II). For this, response surface models of objective and constraint functions were generated, using central composite (CCD) and D-optimal design. The accuracy of approximate models was evaluated through R² value. The obtained optimal solutions by NSGA-II were verified through the TEPC analysis, and we compared the obtained optimum solutions and generated errors from the CCD and D-optimal design. We observed that optimum solutions differ, according to design of experiments (DOE) method.

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Approximate Multi-Objective Optimization of Gap Size of PWR Annular Nuclear Fuels
J. Korean Soc. Precis. Eng.. 2015;32(9):815-824.   Published online September 1, 2015
Download Citation

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Approximate Multi-Objective Optimization of Gap Size of PWR Annular Nuclear Fuels
J. Korean Soc. Precis. Eng.. 2015;32(9):815-824.   Published online September 1, 2015
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