Pressurized Water Reactor Core Parameter Prediction Using an Artificial Neural Network
Author:
Affiliation:
1. Korea Advanced Institute of Science and Technology, Department of Nuclear Engineering 373-1 Kusong-dong, Yusong-gu, Taejon 305-701, Korea
Publisher
Informa UK Limited
Subject
Nuclear Energy and Engineering
Link
https://www.tandfonline.com/doi/pdf/10.13182/NSE93-A23994
Reference9 articles.
1. Construction of Linear Empirical Core Models for Pressurized Water Reactor In-Core Fuel Management
2. A Theory of Fuel Management via Backward Diffusion Calculation
3. Optimization of Core Reload Design for Low-Leakage Fuel Management in Pressurized Water Reactors
4. An Intelligent Stochastic Optimization Routine for Nuclear Fuel Cycle Design
5. A Knowledge-Based System for Optimization of Fuel Reload Configurations
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