蒙特卡罗模拟辅助下中子剂量计对大气宇宙辐射响应的测定

DETERMINATION OF THE RESPONSE TO THE ATMOSPHERIC COSMIC RADIATION OF A NEUTRON DOSIMETER ASSISTED BY MONTE CARLO SIMULATION.

作者信息

Pereira M A, Federico C A, Gonçalez O L

机构信息

Instituto Tecnológico de Aeronáutica, Praça Marechal do Ar Eduardo Gomes, 50, Vila das Acácias, São José dos Campos, São Paulo, Brazil.

Instituto de Estudos Avançados, Trevo Coronel Aviador José Alberto Albano do Amarante, 1, São José dos Campos, São Paulo, Brazil.

出版信息

Radiat Prot Dosimetry. 2018 Oct 1;181(2):142-148. doi: 10.1093/rpd/ncx309.

DOI:10.1093/rpd/ncx309

PMID:29378015

Abstract

A TLD-based dosimeter of polyethylene-lead-polyethylene, was developed and characterized with Monte Carlo simulations, using the MCNPX code. This passive system for the determination of the ambient dose equivalent (H*(10)) for neutrons over a wide energy range can be used for the dosimetry of neutrons from atmospheric cosmic radiation, on the ground, and onboard aircraft. A method assisted by Monte Carlo simulations that improves the calibration of fast neutron dosimeters based on moderation and thermalization of the incident fast flux and the measurement of the thermal flux by a sensor, which respond mainly to thermal neutrons, is presented in this work. The H*(10) energy response of this dosimeter was obtained from simulations for monoenergetic neutrons from 10-10 to 104 MeV. The validation of the modeling was done with irradiations for ISO standard neutron fields of 241Am-Be, 252Cf and 252Cf(D2O) at Instituto de Radioproteção e Dosimetria (IRD, Brazil) and at CERN-EU high-energy reference field (CERF).

摘要

开发了一种基于热释光剂量计的聚乙烯-铅-聚乙烯装置，并使用MCNPX代码通过蒙特卡罗模拟对其进行了表征。这种用于在宽能量范围内测定中子环境剂量当量（H*(10)）的无源系统，可用于地面和飞机上大气宇宙辐射中子的剂量测定。本文介绍了一种由蒙特卡罗模拟辅助的方法，该方法基于入射快中子通量的慢化和热化以及主要对热中子响应的传感器对热通量的测量，改进了快中子剂量计的校准。该剂量计的H*(10)能量响应是通过对能量范围从10⁻¹⁰到10⁴ MeV的单能中子进行模拟得到的。在巴西辐射防护与剂量测定研究所（IRD）以及欧洲核子研究中心-欧盟高能参考场（CERF），利用²⁴¹Am-Be、²⁵²Cf和²⁵²Cf(D₂O)的ISO标准中子场进行辐照，对模型进行了验证。