(3/6) Tallies and Criticality Calculations using Monte Carlo Codes (MCNP, SERPENT & OpenMC)

[@shathaalyazori4607]

Dr. Abdelfattah, could you please upload the rest of this useful set of videos.

[@Sa_1747]

sir please add subtitles

[@Fuad_]

Please turn on captions.I need to autotranslate the video to understand

[@farheenjawaid6260]

Can someone please upload subtitles in English for this

[@jawadabdulhasan5102]

Would you please upload 4/6 , 5/6 and 6/6 videos

[@abdelfattahsoliman4458]

Sure, but these videos are part of online lectures, and I didn’t deliver it yet. I think I’ll deliver these lectures before 2020. It will be part of the playlist named “Neutronic Calculations Lines for Reactor Design & Safety.” Because first I had to explain what’s reactor calculation lines and reactor safety criteria, which are the first two lectures in the playlist. Lectures 3,4,5 in this playlist will be the same as 4/6 5/6 6/6 in the Monte Carlo playlist. Best regards,

[@jawadabdulhasan5102]

@@abdelfattahsoliman4458 Thank you very much indeed

[@farheenjawaid6260]

@@abdelfattahsoliman4458 Can you please share these videos of yours in English, Arabic is not even such a renowned language that one can get someone to translate for them. And this information is quite scarce on the internet, it can be a huge help to other people internationally. This would really be a huge help from your side.