Radiation shielding and thermal analysis of dry cask for training, research, isotopes general atomics reactor spent nuclear fuel using monte carlo N-particle and solidworks simulation codes /

Radiation shielding and thermal analysis of dry cask for training, research, isotopes general atomics reactor spent nuclear fuel using monte carlo N-particle and solidworks simulation codes /

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Bibliographic Details
Main Authors: Nurlaila Syamsul Bahri, 1994-, author 655921, Jasman Zainal, supervisor 556603, Nur Syazwani Mohd. Ali, supervisor 655922, Khairulnadzmi Jamaluddin 1994- author, supervisor 638061, Fakulti Kejuruteraan Kimia dan Kejuruteraan Tenaga 599090
Format: text
Language:eng
Published: Johor Bahru, Johor : Universiti Teknologi Malaysia, 2024

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