辐射变色薄膜剂量计性能测试及加速器应用

本课题的目的是建立用于辐射加工高剂量水平吸收剂量测量的辐射变色薄膜剂量计。通过系统研究,批量制备了以尼龙为基材,副品红氰化物为染料的辐射变色薄膜剂量计。为了验证批制辐射变色薄膜剂量测量的可靠性,选择了国际上应用较广的FWT-60膜及丙氨酸薄膜剂量计与本实验室批制的辐射变色薄膜开展实验室内剂量比对,比对结果均在±4%内符合,归一化偏差En绝对值均小于1。通过在加速器上进一步应用实验表明批制辐射变色薄膜可用于电子束辐照参数测量。     

卫星搭载样品宇宙辐射剂量测量

本工作利用LiF(Mg, Cu, P), 荧光玻璃剂量计和CR-39塑料核径迹探测器对卫星舱内6个搭载实验样品所接受的宇宙辐射剂量进行测量.剂量计均经过严格筛选和标定.通过理论计算, 把以mR单位标定数据变换为肌肉组织的吸收剂量, LiF和荧光玻璃的变换系数分别为0.995和0.93.测量的卫星舱内平均累积剂量为0.88mGy, 平均日剂量为0.11mGy.CR-39记录到许多带电粒子径迹.文中对本次测量结果同以前的测量进行了对比分析讨论.      

卫星舱内两类剂量计测量结果的比较

本文利用1994年和1996年两次返回式卫星的搭载条件对舱内辐射剂量进行了对比测量．通过对比测量,研究不同掺杂、不同厚度LiF剂量计测量空间辐射剂量的特点;研究GM计数管计数和LiF剂量间的转换系数以及转换系数随屏蔽状况的变化;由剂量和GM计数研究粒子平均碰撞阻止本领的估计方法．结果表明,不同掺杂、不同厚度的LiF剂量计测量结果间无显著差异,而转换系数几乎不受舱内位置和屏蔽状态的影响．不同厚度LiF剂量计,不同屏蔽状态的GM计数管计数和剂量—计数转换系数的比较研究以及对粒子平均碰撞阻止本领的估计表明,舱内辐射剂量起决定作用的是高能粒子成分,其平均碰撞阻止本领估计约为5MeV／cm．     

空间辐射剂量测量技术发展CSCD

简要介绍了用于空间辐射剂量测量的被动式和主动式仪器,并进行了对比。被动式仪器有荧光探测器、径迹蚀刻探测器、核乳胶探测器、金属箔探测器、气泡探测器和MOSFET剂量计;主动式仪器有硅半导体探测器(Liulin-4)、硅望远镜(DOSTEL、RRMD、Liulin-5、CPDS)、气体探测器(TEPC、R-16电离室)和中子谱仪(Bonner球中子谱仪、层叠闪烁谱仪)。利用多种测量方法互相补充和验证,为空间辐射剂量提供了更可靠的数据。     

载人航天器舱内辐射剂量及其预估

本文依据国内外95例空间飞行氟化锂热释光剂量计测量的舱内宇宙辐射剂量及轨道参数,建立了近地轨道载人航天器舱内剂量预先评估的数学模型。模型表明,影响舱内剂量水平的主要因素是轨道高度,呈二次曲线形式;其次是太阳活动因素。轨道倾角对舱内剂量的影响并不显著。依据模型作出了辐射安全飞行的时限曲线并就辐射的安全防护问题进行了分析讨论。     

法拉第简法校准丙氨酸对质子吸收剂量技术研究

从低能质子入手,采用基于法拉第简的质子吸收剂量校准方法,满足空间辐射对质子吸收剂量的校准需求。建立了一套法拉第筒法对薄膜剂量计的质子吸收剂量校准系统,该系统由束斑观测单元、束流散射单元、束流监测单元、旋转靶室以及法拉第筒探测单元组成,同时开展了法拉第筒法对丙氨酸薄膜剂量计的质子吸收剂量校准技术研究。     

法拉第筒法校准丙氨酸对质子吸收剂量技术研究

从低能质子入手,采用基于法拉第筒的质子吸收剂量校准方法,满足空间辐射对质子吸收剂量的校准需求。建立了一套法拉第筒法对薄膜剂量计的质子吸收剂量校准系统,该系统由束斑观测单元、束流散射单元、束流监测单元、旋转靶室以及法拉第筒探测单元组成,同时开展了法拉第筒法对丙氨酸薄膜剂量计的质子吸收剂量校准技术研究。     

飞行弹丸红外特性的地面模拟试验

设计并建立了用于飞行弹丸中段飞行状态实验室模拟的试验系统,测量获得了飞行弹丸的红外辐射特性.基于传热与辐射理论,分析了相关参数对实验结果的影响,获得飞行弹丸在一定飞行状态下的辐射特性变化规律.目标的初始温度和辐照条件是影响目标辐射特性的主要因素,自旋状态影响辐射特性的空间分布.试验测量与数值仿真和理论分析结果均具有很好的一致性,证明在实验室开展飞行弹丸的红外辐射特性模拟试验具有可行性.     

中国1987—1990年科学实验卫星中空间辐射剂量信息的热释光分析方法

本文介绍了实验卫星中空间辐射剂量信息的热释光分析方法。应用LiF(Mg,Cu,P)探测器及程序加热方法,分析测定了几次实验卫星中空间辐射日平均剂量,均在20mrad/d以下。应用LiF(Mg,Ti)和Caso_4(Tm)探测器及发光曲线反卷积分析方法,研究了探测器本底荧光与低温峰影响的减除技术和高LET粒子造成的微观剂量分布不均匀情况。     

便携式γ射线照射装置散射辐射特性研究

便携式γ射线照射装置对于提高固定式X、γ辐射剂量仪检定率、解决现场校准难题具有重要意义,利用蒙特卡罗模拟与实验测量协同开展便携式γ射线照射装置散射辐射特性研究。结果表明：蒙特卡罗方法可以模拟得到装置自身的散射辐射,实验测量只能获得照射装置以外辐射场中的散射辐射。利用MCNP程序F4卡和CF卡得到距放射源1 m处照射装置自身的散射贡献分别为13.07 %和4.55 %;反平方律实验和移出实验得到辐射场散射辐射贡献分别为0.2 %和3.94 %,满足ISO 4037-1:2019和GB/T 12162.1-2000的要求。该装置可用于固定式X、γ辐射剂量仪的现场校准。     

Austrian dose measurements onboard space station MIR and the International Space Station--overview and comparison.

The Atominstitute of the Austrian Universities has conducted various space research missions in the last 12 years in cooperation with the Institute for Biomedical Problems in Moscow. They dealt with the exact determination of the radiation hazards for cosmonauts and the development of precise measurement devices. Special emphasis will be laid on the last experiment on space station MIR the goal of which was the determination of the depth distribution of absorbed dose and dose equivalent in a water filled Phantom. The first results from dose measurements onboard the International Space Station (ISS) will also be discussed. The spherical Phantom with a diameter of 35 cm was developed at the Institute for Biomedical Problems and had 4 channels where dosimeters can be exposed in different depths. The exposure period covered the timeframe from May 1997 to February 1999. Thermoluminescent dosimeters (TLDs) were exposed inside the Phantom, either parallel or perpendicular to the hull of the spacecraft. For the evaluation of the linear energy transfer (LET), the high temperature ratio (HTR) method was applied. Based on this method a mean quality factor and, subsequently, the dose equivalent is calculated according to the Q(LET infinity) relationship proposed in ICRP 26. An increased contribution of neutrons could be detected inside the Phantom. However the total dose equivalent did not increase over the depth of the Phantom. As the first Austrian measurements on the ISS dosimeter packages were exposed for 248 days, starting in February 2001 at six different locations onboard the ISS. The Austrian dosimeter sets for this first exposure on the ISS contained five different kinds of passive thermoluminescent dosimeters. First results showed a position dependent absorbed dose rate at the ISS.     

Dosimetric results on EURECA.

Detector packages were exposed on the European Retrievable Carrier (EURECA) as part of the Biostack experiment inside the Exobiology and Radiation Assembly (ERA) and at several locations around EURECA. The packages consist of different plastic nuclear track detectors, nuclear emulsions and thermoluminescence dosimeters (TLDs). Evaluation of these detectors yields data on absorbed dose and particle and linear energy transfer (LET) spectra. Behind a shielding thickness in front of the detectors of 0.09g cm-2 the doses range between 21.26 Gy and 0.87 Gy depending on the location of the dosimeter. Not all measurement can be explained by calculations.     

Verification of shielding effect by the water-filled materials for space radiation in the International Space Station using passive dosimeters

The dose reduction effects for space radiation by installation of water shielding material (“protective curtain”) of a stack board consisting of the hygienic wipes and towels have been experimentally evaluated in the International Space Station by using passive dosimeters. The averaged water thickness of the protective curtain was 6.3 g/cm². The passive dosimeters consisted of a combination of thermoluminescent detectors (TLDs) and plastic nuclear track detectors (PNTDs). Totally 12 passive dosimeter packages were installed in the Russian Service Module during late 2010. Half of the packages were located at the protective curtain surface and the other half were at the crew cabin wall behind or aside the protective curtain. The mean absorbed dose and dose equivalent rates are measured to be 327 μGy/day and 821 μSv/day for the unprotected packages and 224 μGy/day and 575 μSv/day for the protected packages, respectively. The observed dose reduction rate with protective curtain was found to be 37 ± 7% in dose equivalent, which was consistent with the calculation in the spherical water phantom by PHITS. The contributions due to low and high LET particles were found to be comparable in observed dose reduction rate. The protective curtain would be effective shielding material for not only trapped particles (several 10 MeV) but also for low energy galactic cosmic rays (several 100 MeV/n). The properly utilized protective curtain will effectively reduce the radiation dose for crew living in space station and prolong long-term mission in the future.     

Radiation measured during ISS-Expedition 13 with different dosimeters

Radiation in low Earth orbit (LEO) is mainly composed of galactic cosmic rays (GCR), solar energetic particles and particles in SAA (South Atlantic Anomaly). The biological impact of space radiation to astronauts depends strongly on the particles’ linear energy transfer (LET) and is dominated by high LET radiation. It is important to measure the LET spectrum for the space radiation field and to investigate the influence of radiation on astronauts. At present, the preferred active dosimeters sensitive to all LET are the tissue equivalent proportional counter (TEPC) and the silicon detectors in various configurations; the preferred passive dosimeters are CR-39 plastic nuclear track detectors (PNTDs) sensitive to high LET and thermoluminescence dosimeters (TLDs) as well as optically stimulated luminescence dosimeters (OSLDs) sensitive to low LET. The TEPC, CR-39 PNTDs, TLDs and OSLDs were used to investigate the radiation field for the ISS mission Expedition 13 (ISS-12S) in LEO. LET spectra and radiation quantities (fluence, absorbed dose, dose equivalent and quality factor) were measured for the space mission with different dosimeters. This paper introduces the role of high LET radiation in radiobiology, the operational principles for the different dosimeters, the LET spectrum method using CR-39 detectors, the method to combine the results measured with TLDs/OSLDs and CR-39 PNTDs, and presents the LET spectra and the radiation quantities measured and combined.     

A new thermoluminescent dosimeter system for space research

A small, portable, vibration and shock resistant thermoluminescent dosimeter system was developed to measure cosmic radiation dose on board a spacecraft. The system consists of a small battery-operated reader and a special bulb dosimeter. Doses from 10 μGy up to 100 mGy can be measured. The electrical power consumption of the reader is about 5 W, its volume is about 1 dm³ and its mass is about 1 kg. Details are given for the construction and technical parameters of the dosimeter and reader.     

Investigation of dose and flux dynamics in the Liulin-5 dosimeter of the tissue-equivalent phantom onboard the Russian segment of the International Space Station.

Described is the Liulin-5 active dosimetric telescope designed for measurement of the space radiation dose depth-distribution in a human phantom on the Russian Segment of the International Space Station (ISS). The Liulin-5 experiment is a part of the international project MATROSHKA-R on ISS. The MATROSHKA-R project is aimed to study the depth-dose distribution at the sites of critical organs of the human body, using models of human body-anthropomorphic and spherical tissue-equivalent phantoms. The aim of Liulin-5 experiment is a long term (4-5 years) investigation of the radiation environment dynamics inside the spherical tissue-equivalent phantom, mounted in different compartments. Energy deposition spectra, linear energy transfer spectra, and flux and dose rates for charged particles will be measured simultaneously with near real time resolution at different depths of the phantom by means of three silicon detectors. Data obtained together with data from other active and passive dosimeters will be used to estimate the radiation risk to the crewmembers, which verify the models of radiation environment in low Earth orbit. Presented are the test results of the prototype unit. Liulin-5 will be flown on the ISS in the year 2003.     

Peculiarities of the solar proton events of 19 October 1989 and 23 March 1991 according to the measurements onboard the Mir space station.

Flux and dose rate dynamics of solar cosmic rays were measured by the Lyulin dosimeter during the events 19 October 1989 and 23 March 1991. The maximum dose rate registered was 0.4, 0.12 and 0.01 cGy/hour, respectively. Based on the latitude distribution of particle flux a power law form for the energy spectra of solar protons in the anisotropic phase of the events on 19 October 1989 and 23 March 1991 was determined. It was obtained that after the development of geomagnetic storm protons with energies more than 1 GeV were registered.     

Radiation biodosimetry: applications for spaceflight.

The multiparametric dosimetry system that we are developing for medical radiological defense applications could be adapted for spaceflight environments. The system complements the internationally accepted personnel dosimeters and cytogenetic analysis of chromosome aberrations, considered the best means of documenting radiation doses for health records. Our system consists of a portable hematology analyzer, molecular biodosimetry using nucleic acid and antigen-based diagnostic equipment, and a dose assessment management software application. A dry-capillary tube reagent-based centrifuge blood cell counter (QBC Autoread Plus, Becton [correction of Beckon] Dickinson Bioscience) measures peripheral blood lymphocytes and monocytes, which could determine radiation dose based on the kinetics of blood cell depletion. Molecular biomarkers for ionizing radiation exposure (gene expression changes, blood proteins) can be measured in real time using such diagnostic detection technologies as miniaturized nucleic acid sequences and antigen-based biosensors, but they require validation of dose-dependent targets and development of optimized protocols and analysis systems. The Biodosimetry Assessment Tool, a software application, calculates radiation dose based on a patient's physical signs and symptoms and blood cell count analysis. It also annotates location of personnel dosimeters, displays a summary of a patient's dosimetric information to healthcare professionals, and archives the data for further use. These radiation assessment diagnostic technologies can have dual-use applications supporting general medical-related care.