scholarly journals Design, construction and characterization of a portable irradiator to calibrate installed ambient dose equivalent monitors

Author(s):  
C. Oliveira ◽  
J. Cardoso ◽  
A. Carvalho ◽  
L. Santos
2020 ◽  
Vol 30 (1) ◽  
pp. 71
Author(s):  
Le Ngoc Thiem ◽  
Nguyen Ngoc Quynh ◽  
Dang Thi My Linh ◽  
Phan Thi Huong

This paper presents the development of simulated workplace neutron standard fields at the Institute for Nuclear Science and Technology with the 241Am-Be source moderated by polyethylene spheres with diameters of 15 cm and 30 cm. The characterization of the standard fields (in terms of neutron fluence rates and neutron ambient dose equivalent rates) was performed using Bonner sphere spectrometer system together with MAXED and FRUIT unfolding codes. The related quantities such as neutron dose equivalent-averaged energies and fluence-to-ambient dose equivalent conversion coefficients were also determined. The discrepancies of values are satisfied the standard uncertainty criteria as recommended by the International Standard Organization 12789 series. It implies that the simulated workplace neutron standard fields can be applied in the practical works for calibration purposes.


2021 ◽  
Vol 7 (2) ◽  
pp. 16-24
Author(s):  
Ngoc Toan Tran ◽  
Vu Long Chu ◽  
Duc Ky Bui ◽  
Duc Kien Nguyen ◽  
Duc Tam Nguyen

An automated panoramic irradiator with a 241Am-Be neutron source of 5 Ci is installed in a bunker-type medium room at the Institute for Nuclear Science and Technology (INST) for calibration of neutron devices. Bonner Sphere Spectrometer (BSS) formed by 6 spheres plus bare detector, with cylindrical, almost point like, 6LiI(Eu) scintillator and 2 different spectral unfolding FRUIT and BUNKIUT codes are used to characterize the neutron field in different measurement points along the irradiation bench. The neutron field is also simulated by MCNP5 software and compared with measurements performed by the BSS. The paper shows the main results obtained in terms of neutron spectra at fixed distances from the source as well as their neutron fluence rate (totaland direct) and ambient dose equivalent rate. These values measured by the BSS with two unfolding FRUIT and BUNKIUT codes are in good agreement with that of simulated by MCNP5 within 10%.


2019 ◽  
Vol 210 ◽  
pp. 105813 ◽  
Author(s):  
Masaki Andoh ◽  
Satoshi Mikami ◽  
Shuichi Tsuda ◽  
Tadayoshi Yoshida ◽  
Norihiro Matsuda ◽  
...  

2019 ◽  
Vol 6 (0) ◽  
pp. 152-155
Author(s):  
Katsuya Hoshi ◽  
Norio Tsujimura ◽  
Tadayoshi Yoshida ◽  
Osamu Kurihara ◽  
Eunjoo Kim ◽  
...  

2019 ◽  
Vol 21 ◽  
pp. 169
Author(s):  
M. Fakinou ◽  
I. E. Stamatelatos ◽  
J. Kalef-Ezra

Neutron streaming along the labyrinth of a generic bunker of an 18MV medical accelerator was evaluated. Monte Carlo simulations using MCNP code were performed to calculate neutron ambient dose equivalent along the labyrinth. The effect of plain, borated and barites concrete wall material, as well as borated concrete and plywood (Celotex), as neutron absorbing wall liners, was examined. The results of the study suggest that plywood can provide a cost effective material to attenuate neutron streaming along the labyrinth.


Sign in / Sign up

Export Citation Format

Share Document