PWR_BWR HeatGeneration_HeatFlux_NuclearReactors
版本 3.1.0.0 (9.9 KB) 作者:
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.
引用格式
Mateo Ramirez (2024). PWR_BWR HeatGeneration_HeatFlux_NuclearReactors (https://www.mathworks.com/matlabcentral/fileexchange/65352-pwr_bwr-heatgeneration_heatflux_nuclearreactors), MATLAB Central File Exchange. 检索来源 .
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- Sciences > Material Sciences > Thermal Analysis >
- Sciences > Physics > Particle & Nuclear Physics >
- Engineering > Nuclear Engineering > Nuclear Reactor >
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