
Monte Carlo simulation study on the 241Am-Be radionuclide source reference neutron radiation
Author(s) -
Yixin Liu,
Song Zhang,
Yi-Kun Qian,
Yu-Chen Huang,
Mao Benjiang,
Peng Feng,
Zhiqiang Chen
Publication year - 2020
Publication title -
nuclear technology and radiation protection
Language(s) - English
Resource type - Journals
SCImago Journal Rank - 0.31
H-Index - 16
eISSN - 1452-8185
pISSN - 1451-3994
DOI - 10.2298/ntrp2004283l
Subject(s) - neutron , monte carlo method , calibration , radiation , nuclear engineering , equivalent dose , physics , neutron source , nuclear physics , radiation protection , radionuclide , materials science , computational physics , mathematics , engineering , statistics , quantum mechanics
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.