PWR_BWR HeatGeneration_HeatFlux_NuclearReactors
バージョン 3.1.0.0 (9.87 KB) 作成者:
Mateo Ramirez
General Calculations to determine heat generation/flux for nuclear reactor type BWR/PWR
+ Calculations for:
- equivalent core diameter and core length
- average core power density Q'" (MW/m3)
- core-wide average linear heat-generation rate of a fuel rod
- core-wide average heat flux at the interface between the rod and the coolant
Basic Input and Output box dialogues.
引用
Mateo Ramirez (2025). PWR_BWR HeatGeneration_HeatFlux_NuclearReactors (https://www.mathworks.com/matlabcentral/fileexchange/65352-pwr_bwr-heatgeneration_heatflux_nuclearreactors), MATLAB Central File Exchange. に取得済み.
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