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研究堆设施中的个人中子剂量测定

Personal neutron dosimetry at a research reactor facility.

作者信息

Kamenopoulou V, Carinou E, Stamatelatos I E

机构信息

Greek Atomic Energy Commission, P.O. Box 60092, Ag. Paraskevi 15310, Greece.

出版信息

Radiat Prot Dosimetry. 2001;96(1-3):197-200. doi: 10.1093/oxfordjournals.rpd.a006580.

Abstract

Individual neutron monitoring presents several difficulties due to the differences in energy response of the dosemeters. In the present study, an individual dosemeter (TLD) calibration approach is attempted for the personnel of a research reactor facility. The neutron energy response function of the dosemeter was derived using the MCNP code. The results were verified by measurements to three different neutron spectra and were found to be in good agreement. Three different calibration curves were defined for thermal, intermediate and fast neutrons. At the different working positions around the reactor, neutron spectra were defined using the Monte Carlo technique and ambient dose rate measurements were performed. An estimation of the neutrons energy is provided by the ratio of the different TLD pellets of each dosemeter in combination with the information concerning the worker's position; then the dose equivalent is deduced according to the appropriate calibration curve.

摘要

由于剂量计能量响应存在差异,个体中子监测面临若干困难。在本研究中,尝试为某研究堆设施的工作人员采用个体剂量计(热释光剂量计)校准方法。利用MCNP代码推导剂量计的中子能量响应函数。通过对三种不同中子能谱的测量对结果进行验证,发现两者吻合良好。针对热中子、中能中子和快中子定义了三条不同的校准曲线。在反应堆周围不同工作位置,采用蒙特卡罗技术定义中子能谱并进行环境剂量率测量。通过结合每个剂量计不同热释光剂量元件的比例以及工作人员位置信息来估算中子能量;然后根据适当的校准曲线推导出剂量当量。

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