Preliminary Study of the Artificial Neural Networks to replace the constitutive equations in the Reactor Safety Analysis Code > Conferences

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Preliminary Study of the Artificial Neural Networks to replace the constitutive equations in the Reactor Safety Analysis Code

Author	오초환, 신성길, 손성민, 김도현, 이정익
Conference	한국원자력학회 창립 50주년 기념 학술대회
Date	20190523

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이전글A preliminary study on steam generator sizing for the sodium-cooled fast reactor KALIMER-600
다음글Compressor Off-design Performance Prediction with the Similitude Concept for Supercritical CO2 Cooled Small Modular Reactor

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Korea Advanced Institute of Science and Technology (KAIST) 291 Daehak-ro Guseong-dong, Yuseong-gu, Daejeon 305-701, Korea / Office: Room 1401, N7-1 (Mechanical Building) TEL : 042 - 350 - 3829 / FAX : 0507 - 083 - 5945 / EMAIL : jeongiklee@kaist.ac.kr Copyright Dept. of Nuclear & Quantum Engineering. All Rights Reserved.

Preliminary Study of the Artificial Neural Networks to replace the constitutive equations in the Reactor Safety Analysis Code > Conferences

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Preliminary Study of the Artificial Neural Networks to replace the constitutive equations in the Reactor Safety Analysis Code

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