中国辐射防护研究院室内外氡水平调查及剂量评价

采用固体径迹法对中国辐射防护研究院室内外氡水平进行了调查,并估算了室内外氡子体及外照射所致成年人有效剂量。结果表明,室内外氡浓度平均值分别为33.6Bq/m~(-3)及13.7Bqm~(-3),平衡因子F值分别为0.4及0.54,室内外氡子体照射所致成年人平均年有效剂量分别为0.93mSv及0.19mSv,γ外照射致年有效剂量分别为0.55及0.08mSv,总年有效剂量1.75mSv。     

海南温泉设施氡及子体浓度测量与所致剂量研究

为了解海南省温泉设施内氡及子体浓度水平以及温泉利用带来的辐射剂量,采用连续测量方法,对海南省4个地区的典型温泉酒店内不同环境空气中氡及其子体浓度开展了现场测量。结果显示:温泉酒店室内氡及其子体的平均浓度分别为(37.7±21.1) Bq/m³和(16.3±13.9) Bq/m³,氡浓度低于世界卫生组织推荐的参考水平和我国现行国标GB 18871—2002规定的室内氡控制水平;温泉酒店室内环境空气中氡子体所致年有效剂量平均值为1.03 mSv,处于我国正常本底水平范围;客房内氡及子体浓度普遍高于酒店大厅和酒店工作人员的工作间,大厅及工作间相对较低的平衡因子佐证通风状态良好,提示温泉酒店内氡浓度与通风状态密切相关;观察到温泉水利用可以导致客房房间内氡浓度暂时性升高。     

成都地区室内氡浓度调查

采用固体核径迹法,对成都市不同建筑类型、建筑结构、装修材料以及不同楼层的100间居室进行了室内氡浓度测量。调查结果表明:成都市居室环境中氡浓度的最高值为177.1 Bq/m3,最低值为8.4 Bq/m3,算术平均值为(39.4±22.9)Bq/m3;不同类型房屋室内氡浓度水平有显著差异;氡及其子体照射所致的人均年有效剂量为0.99 mSv,低于世界平均水平。     

贵阳市地铁一号线氡浓度水平调查及其评估

本文对贵阳市地铁一号线氡浓度水平进行调查和评估,地铁站点的实测氡浓度为3.33～23.22Bq/m3,平衡当量氡浓度为1.33Bq/m3～9.29Bq/m3,低于标准控制值要求,与国内其他城市地铁站氡浓度水平相当。对吸入氡及其子体产生的年均有效剂量进行了估算,氡及其子体所致地铁工作人员个人剂量估算结果为0.11m Sv/a,低于有效剂量目标值要求。从辐射防护最优化角度考虑,应尽可能降低地铁站氡及其子体这一不必要的照射,应在工程勘察阶段、建设阶段、验收阶段和运行阶段采取防氡措施,今后应开展地铁站氡浓度随各种因素的变化规律研究。     

贵阳市地铁一号线氡浓度水平调查及其评估

本文对贵阳市地铁一号线氡浓度水平进行调查和评估,地铁站点的实测氡浓度为3.33～23.22Bq/m³,平衡当量氡浓度为1.33～9.29Bq/m³,低于标准控制值要求,与国内其他城市地铁站氡浓度水平相当。对吸入氡及其子体产生的年均有效剂量进行了估算,氡及其子体所致地铁工作人员个人剂量估算结果为0.11m Sv/a,低于有效剂量目标值要求。从辐射防护最优化角度考虑,应尽可能降低地铁站氡及其子体这一不必要的照射,应在工程勘察阶段、建设阶段、验收阶段和运行阶段采取防氡措施,今后应开展地铁站氡浓度随各种因素的变化规律研究。     

西安某实验楼氡析出水平调查及辐射剂量估算

本文对西安某实验楼氡析出水平进行了调查和辐射剂量估算。结果表明:地面的平均氡析出率为(0.016±0.007)Bq·m-2·s-1,墙面的平均氡析出率为(0.007±0.003)Bq·m~(-2)·s~(-1),室内平均氡浓度为(16.8±3.25)~(43±1.0)Bq/m~3,实验楼氡及其子体对实验室公众年均有效剂量为0.121~0.310 mSv/a。墙面氡的析出受地下土壤氡浓度影响较小,地面氡的析出受地下土壤氡浓度影响较大,氡浓度和年均有效剂量都未超过国家规定的控制标准。     

西安市地铁车站氡浓度调查与分析

为了了解西安地铁一号线和地铁二号线车站空气中氡浓度水平现状,采用Model 1027连续测氡仪对西安市两条地铁线路车站内氡浓度进行了监测,按照联合国原子辐射效应科学委员会推荐的评价方法估算了车站内氡及其子体所致地铁工作人员人均年有效剂量。监测结果表明,西安市地铁一号线全线氡浓度平均值为60.27 Bq/m3,地铁二号线全线氡浓度平均值为32.54 Bq/m3。地铁一号线和二号线车站内工作人员由氡及其衰变子体所致人均年有效剂量分别为0.63 m Sv/a和0.34 m Sv/a,低于国家标准规定的工作人员年有效剂量限值。     

中国原子能科学研究院典型居民住宅室内氡浓度的调查及其所致居民剂量的估算

我们于1990年1—2月用固体核径迹探测器,抽样调查了原子能院80户居民住宅室内空气中的氡浓度。调查结果表明,我院居民住宅室内氡浓度的范围为16—209Bq/m~3,算术平均值为49Bq/m~3,中位值为38Bq/m~3,调查数据近似服从对数正态分布,几何平均值为41Bq/m~3。由此估算的我院居民因氡及其子体照射所致的个人年有效剂量当量的均值为1.4mSv。     

山东省煤矿氡浓度水平调查与评价

对选取的22个不同类型的山东省煤矿井下氡浓度、γ辐射剂量率及煤中放射性核素含量进行了调查与测量,估算了井下矿工受到的辐射剂量。结果表明,山东省国有大中型煤矿井下氡浓度、γ辐射剂量率、井下矿工人年均有效剂量分别为(48.53±45.87)Bq/m3、(0.199±0.017)μGy/h、0.571 mSv;地方中小型煤矿分别为(63.97±89.18)Bq/m3、(0.144±0.026)μGy/h、0.601 mSv。以上结果表明,山东省煤矿井下氡浓度、γ辐射水平均处于较低水平。     

长沙市地铁一号线车站内氡活度浓度的调查与评价

为了调查长沙市地铁一号线车站内氡活度浓度水平,采样典型抽样法,随机抽取5个车站对其中的氡活度浓度进行测量及评价。借助于径迹蚀刻片,用累积法对车站内的车控室、站台、客服中心的氡活度浓度进行调查。结果表明,长沙市地铁1号线车站内氡活度浓度的范围为22.5～53.0 Bq/m³,均值为35.3 Bq/m³,与长沙市室内氡活度浓度平均值(37.4 Bq/m³)的偏差仅为5.6%,远低于国家现行标准《公共地下建筑及地热水应用中氡的放射防护要求》(WS/T 668—2019)的限制要求;车站内氡活度浓度所致工作人员及公众的年均有效剂量分别为0.28 mSv和0.08 mSv,地铁内的氡气所致工作人员及公众年均有效剂量处在本底水平范围内,满足《电离辐射防护与辐射源安全基本标准》(GB 18871—2002)的限制要求。     

医源性电离辐射损伤及其生物医学防护

随着核与辐射技术在医学检查、诊断和治疗领域运用的增加,世界范围受照人群不断增多,医源性辐射已成为人类最主要的人工辐射来源之一。医疗机构和个人在选择利用放射手段获取诊断和治疗利益的同时,需要注意和防护伴随的辐射损伤效应。本文介绍了医源性辐射及其危害、机体组织的辐射损伤特性和类型、辐射生物效应分子及效应调节研究的进展,简要概述目前临床已经使用或最具应用潜力的辐射防护策略。     

Distribution and Fixation of Cesium and Strontium in Zeolite A and Chabazite

The selective removal and fixation of Cs and Sr have been studied in zeolite A and chabazite. Cesium ion was preferentially distributed into chabazite with a high distribution coefficient (K _Cs>10³ cm³·g^?1) in the presence of NaCl (10^?1 mol·dm^?3). The K _Sr values for zeolite A attained about 10³ cm³·g^?1 in the pH range of 8～10, and they gradually decreased with an decrease in pH.

The initial rate of Cs adsorption was fairly fast in chabazite, and the adsorption ratio reached almost 100% within a few hours. The adsorption ratio of Sr in binderless A zeolite reached almost 100% after 15 h. The adsorption of Cs and Sr on these zeolites was followed by Langmuir-type isotherm. Cesium forms of these zeolites recrystallized to pollucite (CsAlSi₂O₆) above 900°C for zeolite A and above 1,200°C for chabazite. As for Sr forms, these zeolites changed to SrAl₂Si₂O₆ above 900°C.

These recrystallized phases were suitable hosts for the immobilization of Cs and Sr in the nuclear waste solutions.     

全国核与辐射安全监管信息系统的研究和建议

文章简要介绍了全国核与辐射安全监管信息系统的前期规划建设情况,包括基本建设内容、系统总体架构、以及工作中发现的影响和制约工作开展的主要问题,并提出了建议。     

Development and diversity and defense-in-depth application of ABWR feedwater pump and controller model

This work developed an advanced boiling water reactor (ABWR) feedwater pump and controller model, which was incorporated into Personal Computer Transient Analyzer (PCTran)-ABWR, a nuclear power plant simulation code. The feedwater pump model includes three turbine-driven feedwater pumps and one motor-driven feedwater pump. The feedwater controller includes a one-element/three-element water level controller and a specific feedwater speed controller for each feedwater pump. The performance tests, including step change of dome pressure, feedwater pumps transfer, inadvertent closure of all turbine control valves, and one feedwater pump trip at 100% power, demonstrate the feasibility of dynamic response of stand-alone model and incorporated model. Furthermore, a diversity and defense-in-depth analysis is performed to demonstrate the feasibility for motor-driven feedwater pump as an emergency core cooling system (ECCS) automatic diverse back-up. In Lungmen nuclear power plant (NPP), a diverse manual initiation means for the high pressure core flooder (HPCF) loop C is designed as the back-up of digitalized engineered safety features actuation system (ESFAS). If the motor-driven feedwater pump (MDFWP) can be an automatic digital diverse back-up for ESFAS, Lungmen NPP would be more robust to defend against software common-cause failure (CCF).     

清洁解控和退役若干动向与新发展

对国际辐射防护协会第 1 0届大会 ( IRPA-1 0 )涉及的清洁解控和退役问题作了论述 ,包括排除、豁免、清洁解控和废物最少化 ;退役工程技术的发展 ,包括去污技术、切割解体技术、探测技术 ;介绍了一个研究堆退役例子和加速器退役 ;最后 ,还论及了退役中受关注的一些问题 ,如 :石墨废物、混凝土废物、重水堆退役的氚防护、退役时间和退役废物量等。     

核与辐射风险的认知与沟通

面对公众对核与辐射风险极度敏感的现象,本文阐述了对风险的认知及影响认知程度的因素,介绍了风险沟通的发展阶段和四种类型,并给出了若干有效的风险沟通策略建议。     

Thermophysical and mechanical properties of CrB and FeB

ABSTRACT

Fuel debris in the Fukushima Daiichi nuclear power plant is thought to contain borides that are generated from B₄C control material. In order to successfully devise methods to effectively remove the debris material, characterization of the properties of the fuel debris is essential. This paper presents some of the thermophysical and mechanical properties of two types of borides, FeB and CrB, and compares them with those of Fe₂B and ZrB₂. These are the representative borides that might have been generated in the Fukushima Daiichi (1F) nuclear power plant accident. We observed that the thermal conductivity values of both CrB and FeB are much lower than that of ZrB₂, and are similar to that of Fe₂B. Moreover, the Vickers hardness and fracture toughness of FeB and CrB are almost identical to each other, and similar to those of ZrB₂ and Fe₂B.     

Sorption methods of separating barium and radium,aluminum and gallum,and zirconium and hafnium

Chromatographic methods of separating elements with very similar properties have now been developed. However, a number of these methods are difficult to use industrially as their throughput is low. The efficiency of chromatographic separation methods could be increased considerably by using appropriate complex formers, which decrease the effective concentration of the ions being separated, and,in the first approximation, this is equivalent to a decrease in the amount of elements being separated. The difference in the formation constants of the complex compounds increases the separation coefficient. By investigating chromatographic separation with the use of various complex formers, we found the optimal conditions for separating barium and radium, zirconium and hafnium, and aluminum and gallium. The throughput of these methods, with respect to the macroelement was 15–60 kg/hr per m² of column cross section.     

测温热电偶拔出回收技术及回收处理装置

核电站反应堆测温热电偶回收装置是堆芯热电偶检修、更换、回收的专用设备。本文结合３００ＭＷ反应堆型，介绍了一种结构简单、操作方便、使用安全可靠的热电偶拔出回收技术及回收处理装置。