Halo Neutron Measurement for KOTO Experiment

Author(s):  
Naoki Kawasaki ◽  
Noboru Sasao ◽  
Tadashi Nomura ◽  
Hajime Nanjo ◽  
Daichi Naito ◽  
...  
2021 ◽  
Vol 168 ◽  
pp. 112591
Author(s):  
Masayuki Ohta ◽  
Saerom Kwon ◽  
Satoshi Sato ◽  
Mitsuhiro Maida ◽  
Atsushi Kasugai

2013 ◽  
Vol 63 (11) ◽  
pp. 2080-2084 ◽  
Author(s):  
Hee Seo ◽  
Se-Hwan Park ◽  
Byung-Hee Won ◽  
Seong-Kyu Ahn ◽  
Hee-Sung Shin ◽  
...  

2020 ◽  
Vol 35 (4) ◽  
pp. 283-293
Author(s):  
Yixin Liu ◽  
Song Zhang ◽  
Yikun Qian ◽  
Yuchen Huang ◽  
Benjiang Mao ◽  
...  

In order to study the feasibility of using lightweight 241Am-Be radionuclide reference neutron radiation field for the calibration of neutron measurement instruments, this paper reported the Monte Carlo simulation work on free field reference neutron radiation, standard reference neutron radiation regulated by ISO-8529 series standards and minitype reference neutron radiation we designed. The distributions of dose equivalent rates and neutron energy spectrum in different conditions, such as different room types, different room sizes and different shield materials were the main simulation contents for analyzing the characteristics of the three types of reference neutron radiation. According to the simulation results, theoretical supports were provided for the discussion on the minitype reference neutron radiation for calibration purpose.


2015 ◽  
Vol 80 ◽  
pp. 84-86 ◽  
Author(s):  
Shogo Machii ◽  
Kenichi Kuwabara ◽  
Kunihiro Morishima

1995 ◽  
Vol 231 (1-2) ◽  
pp. 419-422
Author(s):  
M. G. Higgins ◽  
R. N. Henriksen

2018 ◽  
Vol 13 (10) ◽  
pp. P10001-P10001 ◽  
Author(s):  
K. Zhao ◽  
L. Chen ◽  
H.P. Guo ◽  
J.L. Ruan ◽  
S.Y. He ◽  
...  

2020 ◽  
Vol 225 ◽  
pp. 05001
Author(s):  
M. Ben Mosbah ◽  
C. Eleon ◽  
C. Passard ◽  
J. Loridon ◽  
B. Perot ◽  
...  

The knowledge of the fissile material mass is a key challenge to enhance radioactive waste management and to ensure a high level of safety in nuclear industry. Data is analyzed according to the principles of the neutron measurement techniques. As proportional counters filled with 3He gas display high neutron detection efficiency and a good gamma-ray discrimination, they are the reference detector for passive neutron coincidence counting. A charge preamplifier or a current amplifier, depending on applications, collects the electric pulse produced by neutron interaction in the 3He gas and a threshold discriminator produces a logic pulse used for neutron counting. This paper describes the performance assessment of different commercially available electronics from Mirion Technologies, Precision Data Technology (PDT), Mesytec, as well as MONACO electronics originally developed by CEA LIST for fission chamber measurements in experimental reactors. Comparative passive neutron measurements are carried out with these electronics at CEA/DEN Nuclear Measurement Laboratory in Cadarache. Overall, PDT and Mesytec electronics show similar detection efficiency as the ACH-NA98 charge amplifier, which is commonly used in our laboratory for such applications. However, MONACO electronics have a lower detection efficiency, similar to Mirion 7820 current amplifier used in specific high-count rate applications. An optimisation of MONACO settings would probably be necessary to adapt to 3He counters instead of fission chambers.


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