医用放射性设备损伤分析与防护

目的：提出合理的医用放射性设备防护措施，给出进行设备放射性评价的指标。方法：针对放射线的波长、穿透力、荧光作用、摄影作用和生物效应分析放射性形成机制。结果给出放射性防护的基本措施和放射设备防护指标评价要素。结论：认识放射性设备防护原理及措施，有利于充分发挥射线在医学上的巨大作用，有利于合理确定放射设备成本，有利于促进放射技术良性发展。     

某核电厂非放射性职业病危害因素调查

目的掌握某核电厂存在的非放射性职业病危害因素及危害程度,提出职业病防治的重点。方法对某核电厂进行职业卫生学调查、检测及定量分级。结果有3/5噪声岗位的8h等效连续A声级超过国家职业卫生标准;氨、联氨、氢氧化钠、硫酸、盐酸、氯气等6种毒物浓度和工频高压电场强度均符合国家职业卫生标准。结论该核电厂噪声污染较重,应加强非放射性职业危害的防治工作。     

放射免疫实验室的放射性防护

放射免疫实验室是医院检验科主要的实验室,放射免疫室放射免疫试剂的管理,放射免疫分析工作人员的防护,放射性污染以及放射性废物的处理就显得尤为重要。     

放射性皮炎的防护进展

放射治疗是治疗恶性肿瘤的主要手段之一.放射性皮炎是肿瘤放射治疗过程中或结束时较为常见的副反应[1].照射野局部皮肤放疗后会因毛细血管扩张出现红斑、进而出现色素沉着,小血管内微血栓形成导致局部缺氧及继发细胞损伤、死亡,出现脱皮、脱发、溃疡、出血、坏死,或因液体潴留而出现水肿,严重者甚至出现经久不愈的溃疡,常因此中断放疗而影响疗效.近几年,国内学者对放射性皮炎的预防、治疗及护理做了大量的研究,探索了许多方法并取得一定的疗效,现综述如下:     

漳州核电厂周边食品总α和总β放射性本底调查

目的 掌握漳州核电厂运行前周边地区食品总α和总β放射性水平。方法 采集漳州核电厂周边日常食用的5类33种49份样品,对样品前处理、干燥和灰化后,采用低本底α、β测量仪测定其总α、总β放射性,用原子吸收法测量钾和查阅营养膳食系统不同食品中的钾含量来分别计算减钾总β放射性水平。结果 漳州核电厂周边食品中蔬菜水果类、粮食类、家禽家畜类、水产品类、茶叶类放射性总α放射性分别为相似文献   

鼻咽癌患者放射性皮炎的防护及护理

目的探讨鼻咽癌患者放射性皮炎的临床防护和护理方法。方法对在我院住院治疗的100例鼻咽癌患者的临床相关资料进行回顾性分析,对临床治疗本疾病的防护及护理方法进行总结。结果在我院住院治疗的患者中,82例出现放射性皮炎,经过我院恰当的护理,所有患者病情好转。结论对鼻咽癌患者进行适当的护理,有利于患者病情的康复,同时适当的护理对放射性皮炎的治疗有积极的临床治疗作用。     

放射医疗设备的检修方法

根据放射医疗设备的发展,结合笔者多年来从事放射医疗设备检修的实践,对设备的检修方法做了总结。     

用测试仪检修医疗设备故障的原理与分析

医院现代化医疗设备多以集成电路（IC）为主的印刷电路板构成，其维修工作，特别是进口设备在缺少图纸的情况下，就显得更为艰难。本文就利用测试仪未检修设备的原理作一介绍，使复杂的维修工作变得简单、快捷了。     

皮肤防护剂预防放射性皮肤反应的临床观察

目的观察皮肤防护剂预防放射性皮肤反应的临床效果。方法将在荆州市第一人民医院住院的头颈部肿瘤患者94例,按照放疗的初始日期单双号随机分为观察组和对照组,将皮肤防护剂均匀涂于观察组病人的照射野皮肤上,用直线加速器常规照射,观察两组发生放射性皮肤反应情况。结果两组病人放射野皮肤反应程度,经统计学处理,P〈0.01,差异有统计学意义;观察组色素沉着、干性皮炎、湿性皮炎的皮肤损伤体征显著低于对照组;皮肤防护剂还能推迟放射性皮肤反应的发生。结论应用皮肤防护剂,可有效预防放射性皮肤反应,减轻皮肤损害,提高皮肤耐受性,有利于放疗的顺利进行。     

Establishment of radiation protection boundaries for nuclear power plants

Activities involving the possession and use of radioactive material require the application of controls to ensure the health and safety of the worker and general public. One of the first steps in adequately controlling any licensed activity is the establishment of zones and boundaries that will exist for purposes of restricting or regulating personnel radiological exposure. Title 10 of the Code of Federal Regulations, Part 20 (10 CFR 20) defines the "restricted area" (RA) and prescribes the administrative and radiological protection controls pertinent to the RA. For nuclear power facilities, the determination of the physical relation of the RA boundary with other physical or administrative boundaries, such as the site boundary, the radiologically controlled area (RCA), and the exclusion area boundary, must be based on an evaluation that considers all applicable federal requirements and limits for each zone or boundary contained within or interfacing with the RA. This paper presents a discussion of the factors that should be considered and an evaluation methodology that can be utilized based on the generation of two-dimensional isodoses.     

Carbon-14 in low-level radioactive waste from two nuclear power plants

The amount of 14C in low-level radioactive wastes is important for determining the future impacts of their disposal. New regulations in the Code of Federal Regulations, Title 10, Part 61 (10 CFR 61) require quantitation of 14C and other radionuclides in such wastes not amenable to measurement by gamma spectroscopy. Sampling was done of major waste streams at the Palisades pressurized water reactor (PWR) and the Big Rock Point boiling water reactor (BWR) to determine quantities of 14C in the waste streams for comparison with other reported studies. Analyses were performed by releasing all 14C constituents in the waste samples in the form of 14CO2 by chemical processing or by heating the samples in a tube furnace containing CuO2 catalyst and trapping the evolved gas in a liquid scintillator for counting. The largest amounts of 14C were found in the resins and filters used for reactor water cleanup, a result which is similar to those of the available studies. From these data, the annual amounts of 14C in wastes from nominal PWRs and BWRs were estimated to be 4.7 and 0.5 Ci/GW(e)-yr, respectively.     

Occupational radiation exposures during maintenance activities at nuclear power plants

Occupational exposures at nuclear power plants occur mostly during maintenance activities rather than during routine reactor operation. In this paper, statistical summaries of occupational exposures during routine maintenance activities for the years 1982-84 at nuclear power plants in Japan are presented, including comparison of the exposure levels by reactor type and by plant age. Average annual collective doses per reactor for BWRs and PWRs are 7.30 man-Sv and 2.84 man-Sv, respectively, and 78% and 89% of annual doses are incurred during maintenance activities. Average annual outage days of BWRs and PWRs for routine maintenance are 102 d and 97 d. Annual collective doses per reactor, most of which occur during maintenance activities, usually increase with plant age. Higher collective doses are observed for routine maintenance performed on older reactors as compared to newer reactors, especially in BWRs. Collective doses accrued during respective routine maintenance activities have a significant correlation with duration of maintenance and number of workers involved in maintenance.     

Radiation protection at U.S. nuclear power plants--today and tomorrow

The nuclear power industry work ethic and culture is founded on learning from experience and continuously finding ways to improve performance--especially in regard to radiation safety. Over the past 25 y, this process of continuous improvement has yielded exceptional results in regard to radiation protection of workers, the public and the environment. In light of the resurgence of nuclear energy in the United States, the nuclear power industry is developing strategies to achieve continuous improvements to performance and address emerging challenges in the area of radiation protection.     

天然气蒸汽联合循环热电工程职业病危害因素分析

目的识别、分析天然气蒸汽联合循环热电工程的职业病危害因素,确定职业病危害程度,提出防治对策,以保护劳动者职业健康。方法采用现场卫生学调查的方法调查分析企业基本情况、生产工艺、职业病危害因素及职业病危害防护措施;采用工作场所职业病危害因素测定法检测工作场所职业病危害因素的浓度或强度;采用工作场所职业危害分级方法进行工作场所职业病危害分级。结果天然气蒸汽联合循环热电工程存在的主要职业病危害因素为噪声、高温、热辐射、工频超高压电场、CO、CO2、NO、NO2、硫化氢、盐酸、氢氧化钠、氨、联氨、硫酸等;工程采用的生产工艺先进,工人作业方式主要为巡检;职业病危害防护设施设置基本合理;检测结果表明检测的31个噪声作业点中有5个点超标,超标率为16%,循环水泵旁噪声最高为94.4 dB(A);个体噪声及化学毒物检测结果全部符合国家职业卫生标准,运行岗位高温危害分级为Ⅱ级。结论职业病危害关键控制点为噪声和高温。氨、联氨、盐酸、氢氧化钠、硫酸等化学有害因素应加强管理。企业应按照《中华人民共和国职业病防治法》及相关法规、标准要求加强职业病防治工作。     

核电站放射卫生防护标准

为保障核电站工作人员和广大公众的健康安全,促进我国核电事业的发展,特根据国家标准《放射卫生防护基本标准》制定本标准。     

火力发电厂职业病危害及关键控制因素分析

目的 了解火力发电厂职业病危害状况, 为该行业从业人员的职业健康与安全提供参考。
方法 通过对原辅材料和工艺流程的分析, 描述职业病危害因素的分布, 通过现场调查及三家火力发电厂的检测数据分析, 确定职业病危害控制的关键因素。
结果 燃煤发电厂存在着粉尘、噪声、高温、化学毒物(氨、氮氧化物、氟化物、硫酸、氢氧化钠等)、工频电磁场等诸多职业病危害因素, 检测结果显示三家电厂除灰除渣系统、锅炉系统, 以及运煤、制粉系统粉尘存在超标情况, 各工序噪声也均有超标情况; 两家电厂工频电场存在超标情况。
结论 燃煤发电厂关键控制因素为噪声、煤尘、矽尘、工频电场、氨、硫化氢。通过对关键控制因素的重点控制, 需有针对性地进行职业病防护, 保护劳动者的健康。
     

燃煤火力发电厂主要职业病危害因素控制技术进展

燃煤火力发电厂在运行过程中产生粉尘、噪声、毒物等职业病危害因素,而采用合理的控制技术,可有效降低工作场所中职业病危害因素的浓度(强度)。本文基于目前燃煤火力发电厂存在的职业危害控制现状,综述控制该类生产企业中职业病危害因素的主要技术。     

医疗设备开关电源的维修体会

开关型稳压电源（开关电源）具有效率高、体积小、适用面广、可靠性高等特点。符合现代电子设备向小型化发展的方向;因而被广泛采用。相对于电子设备中的其他模块．开关电源工作电压较高、电流较大,故障率高。