Monte Carlo Methods of Neutron Beam Design for Neutron Capture Therapy at the Mit Research Reactor (MITR-II)

Author(s):  
S. D. Clement ◽  
J. R. Choi ◽  
R. G. Zamenhof ◽  
J. C. Yanch ◽  
O. K. Harling
1990 ◽  
Vol 92 (1) ◽  
pp. 106-117 ◽  
Author(s):  
Floyd J. Wheeler ◽  
D. Kent Parsons ◽  
Brian L. Rushton ◽  
David W. Nigg

1992 ◽  
Vol 19 (3) ◽  
pp. 709-721 ◽  
Author(s):  
J. C. Yanch ◽  
X-L. Zhou ◽  
R. E. Shefer ◽  
R. E. Klinkowstein

2019 ◽  
Vol 133 ◽  
pp. S1024
Author(s):  
S. Bortolussi ◽  
I. Postuma ◽  
N. Protti ◽  
S. Fatemi ◽  
C. Magni ◽  
...  

2021 ◽  
Vol 16 (12) ◽  
pp. P12023
Author(s):  
M.J. Mozafari Vanani ◽  
Y. Kasesaz ◽  
M. Hosseinipanah ◽  
A. Akhound

Abstract Tehran Research Reactor (TRR) is the main neutron source in Iran which can be used for different applications of neutrons such as neutron radiography and neutron therapy. TRR has a thermal column which can provide high intensity flux of thermal neutrons for users. The aim of this study is to design a neutron collimator for TRR thermal column to produce parallel neutron beam with suitable intensity of thermal neutrons. To achieve this goal, Monte Carlo code of MCNX has been used to evaluate different configurations, geometries and materials of neutron collimator. The results show that the final selected configuration can provide a uniform thermal neutron beam with a flux of 1.21E+13 (cm-2·s-1) which is suitable for many different neutron applications.


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