Halo Neutron Measurement for KOTO Experiment

2015 ◽  
Author(s):  
Naoki Kawasaki ◽  
Noboru Sasao ◽  
Tadashi Nomura ◽  
Hajime Nanjo ◽  
Daichi Naito ◽  
...  
Keyword(s):  
Neutron Measurement ◽  
Halo Neutron

Conceptual design of radio isotope production module and application for neutron measurement in A-FNS

2021 ◽  
Vol 168 ◽  
pp. 112591
Author(s):  
Masayuki Ohta ◽  
Saerom Kwon ◽  
Satoshi Sato ◽  
Mitsuhiro Maida ◽  
Atsushi Kasugai
Keyword(s):  
Conceptual Design ◽  
Isotope Production ◽  
Neutron Measurement

Development of a neutron measurement system in unified non-destructive assay for the PRIDE facility

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

scholarly journals Monte Carlo simulation study on the 241Am-Be radionuclide source reference neutron radiation

2020 ◽  
Vol 35 (4) ◽  
pp. 283-293
Author(s):  
Yixin Liu ◽  
Song Zhang ◽  
Yikun Qian ◽  
Yuchen Huang ◽  
Benjiang Mao ◽  
...  
Keyword(s):  
Monte Carlo Simulation ◽  
Monte Carlo ◽  
Free Field ◽  
Neutron Radiation ◽  
Neutron Energy Spectrum ◽  
Measurement Instruments ◽  
Dose Equivalent ◽  
Monte Carlo Simulation Study ◽  
Neutron Measurement ◽  
Radionuclide Source

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.

scholarly journals Development of Nuclear Emulsion for Fast Neutron Measurement

2015 ◽  
Vol 80 ◽  
pp. 84-86 ◽  
Author(s):  
Shogo Machii ◽  
Kenichi Kuwabara ◽  
Kunihiro Morishima
Keyword(s):  
Fast Neutron ◽  
Nuclear Emulsion ◽  
Neutron Measurement

scholarly journals Distribution of gamma-ray bursts in halo neutron star-comet models

1995 ◽  
Vol 231 (1-2) ◽  
pp. 419-422
Author(s):  
M. G. Higgins ◽  
R. N. Henriksen
Keyword(s):  
Neutron Star ◽  
Gamma Ray ◽  
Gamma Ray Bursts ◽  
Halo Neutron

Application of stilbene crystals in neutron measurement for monoenergetic neutron beam

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

scholarly journals Performance assessment of amplification and discrimination electronic devices for passive neutron measurements

2020 ◽  
Vol 225 ◽  
pp. 05001
Author(s):  
M. Ben Mosbah ◽  
C. Eleon ◽  
C. Passard ◽  
J. Loridon ◽  
B. Perot ◽  
...  
Keyword(s):  
Performance Assessment ◽  
Detection Efficiency ◽  
Electric Pulse ◽  
Measurement Techniques ◽  
Nuclear Industry ◽  
Fissile Material ◽  
High Count ◽  
Precision Data ◽  
Neutron Measurement ◽  
Current Amplifier

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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