Neutron Beam Design and Performance for BNCT in Czechoslovakia

Author(s):  
J. Burian ◽  
J. Rataj
2019 ◽  
Vol 219 ◽  
pp. 10003 ◽  
Author(s):  
Torsten Soldner ◽  
Hartmut Abele ◽  
Gertrud Konrad ◽  
Bastian Märkisch ◽  
Florian M. Piegsa ◽  
...  

Pulsed beams have tremendous advantages for precision experiments with cold neutrons. In order to minimise and measure systematic effects, they are used at continuous sources in spite of the related substantial decrease in intensity. At the European Spallation Source ESS these experiments will profit from the pulse structure of the source and its 50 times higher peak brightness compared to the most intense reactor facilities, making novel concepts feasible. Therefore, the cold neutron beam facility for particle physics ANNI was proposed as part of the ESS instrument suite. The proposed design has been re-optimised to take into account the present ESS cold moderator layout. We present design considerations, the optimised instrument parameters and performance, and expected gain factors for several reference experiments.


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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