NE410/510 - Lecture 14: Generating Multigroup Cross Sections and Neutron Flux Spectra

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Nuclear Engineering Lectures

Nuclear Engineering Lectures

Күн бұрын

Пікірлер: 6
@shikshokio1
@shikshokio1 Жыл бұрын
This was a magnificent lecture. Thanks!
@ikhwankhaleb3511
@ikhwankhaleb3511 Жыл бұрын
Thanks so much for all of these! I'm starting my masters in nuclear engineering after a few years leaving the academic and these brushed up my memories so much!
@NuclearEngineeringLectures
@NuclearEngineeringLectures Жыл бұрын
Glad that you find these lectures helpful!
@ssh5038
@ssh5038 2 жыл бұрын
Thanks a lot for sharing these lectures. I am new to this field and very much interested to know about neutronic calculation. I would be thankful if You could answer me why exactly the current gradient is zero for homogenous material?
@NuclearEngineeringLectures
@NuclearEngineeringLectures 2 жыл бұрын
The net current is zero for an infinitely homogenous material because the current of neutrons traveling in any one direction is cancelled by the current of neutrons traveling in the opposite direction. If everything is infinite and homogenous, then the directional dependent currents all cancel out.
@rationalbelief4451
@rationalbelief4451 8 ай бұрын
I wish i could have your slides
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