Depletion chain optimization of lattice code STREAM for LWR fuel assembly burnup analysis
Author:
Funder
National Research Foundation of Korea
MSIP
Publisher
Elsevier BV
Subject
Nuclear Energy and Engineering
Reference10 articles.
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2. Investigation and improvement of the Mini-Max Polynomial Approximation method for solving burnup equations;Annals of Nuclear Energy;2023-01
3. Burnup chain compression method preserving neutronics, decay photon source term and decay heat calculation results;Annals of Nuclear Energy;2022-10
4. Performance analysis of nuclear reactor core loaded with Accident-Tolerant Fuel: Mo/Cr metallic microcell UO2 pellets and CrAl coating;Annals of Nuclear Energy;2022-09
5. Problem-dependent compression method for burnup library;Annals of Nuclear Energy;2020-06
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