Simulation of neutron flux in silicon, cadmium and plumbum using Monte Carlo method
The purpose of this study is to investigate the neutron energy flux from reactor after attenuated by silicon, cadmium and plumbum at the end of the beam port. Neutrons can be categorized into thermal neutron, intermediate and fast neutron according to their energies. Fast neutrons in reactor needs t...
Saved in:
主要作者: | Hamzah, Hafida |
---|---|
格式: | Thesis |
語言: | English |
出版: |
2010
|
主題: | |
在線閱讀: | http://eprints.utm.my/id/eprint/11300/4/HafidaHamzahMFS2010.pdf |
標簽: |
添加標簽
沒有標簽, 成為第一個標記此記錄!
|
相似書籍
-
Improvement of neutron collimator design for thermal neutron radiography using Monte Carlo-Particle transport code version 5
由: Supramaniam, Thiagu
出版: (2007) -
Photon energy response of silicon dioxide fibre optic and TLD 100 using Monte Carlo simulation
由: Asni, Hazila
出版: (2011) -
Trimon: An Efficient Multigroup
Monte Carlo Neutron Transport Code
For Triga Reactors
由: Omar, Muhammad Rabie
出版: (2020) -
Adaptive Markov Chain Monte Carlo techniques to estimate vehicle motion
由: Kow, Wei Yeang
出版: (2013) -
Neutron Flux Measurements With Monte Carlo Verification At The Thermal Column Of A Triga Mark II Reactor : Feasibility Study For A BNCT Facility [QC793.5.N462 E34 2008 f rb].
由: Eid Abdel_Munem, Eid Mahmoud
出版: (2008)