ReCLAIM v2.0: a spreadsheet tool for calculating doses and soil/water radionuclide screening levels for assessment of radioactively contaminated land.

This note describes an electronic spreadsheet tool called ReCLAIM v2.0, developed by Nexia Solutions Ltd. The tool calculates doses to exposure groups for assessment of radioactively contaminated land including UK Nuclear Licensed sites on an individual exposure pathway basis and on a multiple exposure pathway basis constituting various specifiable scenarios. It also calculates soil/water screening levels of individual radionuclides with reference to selected exposure pathways and a dose target, and considers radionuclide additivity. Subject to agreement with a ReCLAIM disclaimer, the tool, with accompanying documentation (User Guide and Verification Report), can be downloaded without cost from the website (www.nexiasolutions.com/reclaim).     

P57~(Kip2)及Ki67抗原在水泡状胎块及水肿性流产中的表达特点及意义

目的:探讨P57Kip2及Ki67抗原在水泡状胎块(HM)及水肿性流产(HA)中的表达特点及意义。方法:回顾性搜集HM及HA病例共182例,应用免疫组织化学(免疫组化)染色方法检测P57Kip2及Ki67抗原表达情况,并对病理诊断结果进行重新评估。结果:P57Kip2在完全性水泡状胎块(CHM)中呈阴性表达,ki67高水平表达;P57Kip2在部分性水泡状胎块(PHM)及HA病例中呈阳性表达,Ki67在PHM中以中、高等水平表达,在HA病例中低水平表达;Ki67在PHM与HA病例两两比较,差异具有统计学意义(P<0.01)。结论:P57Kip2及Ki67蛋白可作为HM诊断与分型的一种有效参考指标。     

Panel session on international perspectives on the future of nuclear power

The 2009 National Council on Radiation Protection (NCRP) Annual Meeting provided an opportunity to exchange viewpoints and consider current information regarding the evolution of selected commercial nuclear power trends worldwide. Within the overall topical context of radiation-related regulation, focus was placed on activities in the United Kingdom, Japan, and the United States, although general global developments were reviewed to some extent. This paper provides the reader with a sense of these activities as described by the authors and presenters: David Bennett (Environmental Agency, United Kingdom), Alan Hanson (AREVA), Shojiro Matsuura (Japan Nuclear Safety Research Association), and Alexander Marion (Nuclear Energy Institute).     

Medical response to a nuclear detonation: creating a playbook for state and local planners and responders

For efficient and effective medical responses to mass casualty events, detailed advanced planning is required. For federal responders, this is an ongoing responsibility. The US Department of Health and Human Services (DHHS) prepares playbooks with formal, written plans that are reviewed, updated, and exercised regularly. Recognizing that state and local responders with fewer resources may be helped in creating their own event-specific response plans, subject matter experts from the range of sectors comprising the Scarce Resources for a Nuclear Detonation Project, provided for this first time a state and local planner's playbook template for responding to a nuclear detonation. The playbook elements are adapted from DHHS playbooks with appropriate modification for state and local planners. Individualization by venue is expected, reflecting specific assets, populations, geography, preferences, and expertise. This playbook template is designed to be a practical tool with sufficient background information and options for step-by-step individualized planning and response.     

上海市核和辐射医学救治基地建设回顾与展望

目的 回顾分析上海市核和辐射医学救治基地建设情况,并针对性的提出进一步展望。方法 在文献分析和实地调查的基础上,结合专家意见,归纳分析。结果 上海市核和辐射医学救治基地,在组织体系、预案制度、设备设施、培训演练等方面初具规模,在平战结合、军地结合、信息系统等方面仍需继续完善。结论 上海市核和辐射医疗救治基地初步具备了核和辐射事件的救治能力,但仍需进一步加大投入。     

海阳核电站周边地区环境γ辐射剂量率水平调查与评价

目的 获取海阳核电站运行前周边地区的环境γ辐射剂量率本底数据,为评价核电站运行后对周边环境的影响提供依据。方法 利用GR 460车载辐射监测系统,在海阳核电站周边30 km范围内开展现场巡测,并估算居民暴露剂量。结果 周边环境γ辐射空气吸收剂量率的范围为39.6~109 nGy/h,均值为72.2 nGy/h,距离核电站0~5、5~10、10~20、20~30 km区域内的γ辐射空气吸收剂量率均值间有显著差异性,室外环境γ辐射剂量率所致居民的人均年有效剂量为84.8 μSv。结论 海阳核电站周边地区的环境γ辐射剂量率及其所致居民暴露剂量均属于我国正常本底水平之内。     

Using the IRPA Guiding Principles on Stakeholder Engagement: putting theory into practice

The International Radiation Protection Association (IRPA) published their Guiding Principles for Radiation Protection Professionals on Stakeholder Engagement in February 2009. The publication of this document is the culmination of four years of work by the Spanish Society for Radiological Protection, the French Society of Radioprotection, the United Kingdom Society of Radiological Protection, and the IRPA organization, with full participation by the Italian Associate Society and the Nuclear Energy Agency's Committee on Radiation Protection and Public Health. The Guiding Principles provide field-tested and sound counsel to the radiation protection profession to aid it in successfully engaging with stakeholders in decision-making processes that result in mutually agreeable and sustainable decisions. Stakeholders in the radiation protection decision making process are now being recognized as a spectrum of individuals and organizations specific to the situation. It is also important to note that stakeholder engagement is not needed or advised in all decision making situations, although it has been shown to be a tool of first choice in dealing with such topics as intervention and chronic exposure situations, as well as situations that have reached an impasse using traditional approaches to decision-making. To enhance the contribution of the radiation protection profession, it is important for radiation protection professionals and their national professional societies to embrace and implement the IRPA Guiding Principles in a sustainable way by making them a cornerstone of their operations and an integral part of day-to-day activities.     

An Australian secondary standard dosimetry laboratory participation in IAEA postal dose audits

For over 30 years, the International Atomic Energy Agency (IAEA) and the World Health Organization (WHO) have jointly monitored activities of secondary standard dosimetry laboratories (SSDLs) through postal dose audits with the aim of achieving consistency in dosimetry throughout the world. The Australian Nuclear Science and Technology Organisation (ANSTO) maintains an SSDL and is a member of the IAEA/WHO SSDL Network. Postal dose audit results at this Australian SSDL from 2001 to 2011 demonstrate the consistency of absorbed dose to water measurements, underpinned by the primary standard maintained at the Australian Radiation Protection and Nuclear Safety Agency (ARPANSA).     

Environmental releases of radioactivity and the incidence of thyroid disease at the Ignalina Nuclear Power Plant

The Ignalina Nuclear Power Plant consists of two Russian-made RBMK-1500 reactors. The plant uses Lake Druksiai as a natural reservoir for cooling water. Within the framework of the revised radiation dose limitation system, site-specific routine release conversion factors and maximum annual effective doses for the dominant radionuclides and pathways were evaluated for both atmospheric and aquatic releases. Using calculated release conversion factors, the locations of the highest predicted activity concentrations were determined for air and for the dilution zone of heated effluent water during the period 1984-1998. Committed effective doses for critical group members were less than 0.001 mSv for Ignalina Nuclear Power Plant airborne releases and less than 0.05 mSv for aquatic releases. These dose estimates are lower than the 1 mSv dose limit for the adjacent population. In the case of Ignalina Nuclear Power Plant, taking into account the uncertainties, a recommendation for the administrative dose constraint is 0.25 mSv y(-1). This dose level may scarcely affect human health. Interestingly, during screening for thyroid disorders, endocrinologists and pediatric-endocrinologists determined a dominance of abnormal thyroids (up to 60%) among school children in the vicinity of Ignalina NPP. The data on neonatal screening for congenital hypothyroidism and transient hyperthyrotropinemia, however, suggested a possibility that the majority of abnormal thyroid cases were related to stable iodine deficiency. Thus, the influence of Ignalina Nuclear Power Plant on thyroid disorders is highly conjectural and unlikely to be associated with the observed levels of childhood thyroid disease.     

南宁市医院室内氡浓度及γ辐射水平所致工作人员剂量

目的 了解南宁市医院放射科与核医学科室内氡浓度和γ照射量率水平,估算工作人员受照剂量,为辐射防护管理提供依据。方法 采用ATD累积氡探测器和FH40G环境X、γ剂量率仪测量室内外氡浓度和γ照射量率。结果 核医学、放射科地下和地面工作场所、工作人员和居民受照剂量分别是1.98 mSv、1.84 mSv、1.62 mSv、1.48 mSv和1.49 mSv。结论 核医学科工作人员受到的附加剂量主要与放射性同位素的用量与防护条件有关。放射科工作人员剂量增高的原因主要来自氡污染产生的内照射。     

2008-2015年田湾核电站周围沉降物中总α、总β放射性水平监测

目的 调查田湾核电站地区沉降物中总α、总β放射性水平,并与对照地区沉降物中总α、总β放射性水平进行比较分析,为我省核电站周围总α、总β放射性水平监测网络提供数据支持.方法 根据《辐射环境监测技术规范》(HJ/T 61-2001)要求,分别在距离田湾核电站30和300 km处设置沉降物监测点和对照地区监测点,每个采样点每...     

Assessment of Occupational Exposure Among Pakistani Medical Staff During 2007–2011

The data analysis of occupationally exposed medical workers in Nuclear Medicine (NM), Radiotherapy (RT) and Diagnostic Radiology (DR) at the Institute of Nuclear Medicine and Oncology (INMOL), Pakistan is presented for the time interval (2007-2011). The whole-body exposure doses of the workers were measured by using the Film Badge Dosimetry technique. The annual average effective doses in NM, RT and DR have been found well below the permissible annual limit of 20?mSv (averaged over a period of 5 consecutive years), with no over-exposure detected. This declining trend of annual average effective dose is the consequence of improved radiation protection practices at INMOL during the recent years.     

Comparison of the MCNP calculated and measured radiation field quantities near the RB reactor.

The RB experimental reactor has operated at Vinca Institute of Nuclear Sciences since the end of April 1958. In this paper, neutron and gamma-ray spectra and corresponding dose quantities near the reactor, calculated by using the MCNP code, are compared to the measured values during the Third International Intercomparison Experiment on Nuclear Accident Dosimetry carried out at the RB reactor in 1973. Discrepancies in the correlation declared power of the reactor-dose rates are found. Good agreements are obtained between measured and calculated neutron and gamma-ray spectra, and corresponding absorbed doses in air, but only after the reactor declared power is multiplied by a correction factor, determined in this study.     

中国核电站操纵人员办事风格因素的初步报告

目的 探讨中国核电站操纵人员的办事风格及其与年龄、工龄、学历、婚姻状况等因素的相关性,为核电站安全运行提供科学依据。方法 随机抽取国内7座核电站操纵人员500例,采用苏州大学附属第二医院研发的《中国核电厂操纵人员心理健康和神经行为测评系统2.0版》进行心理测试,获取办事风格因子的分值数据,并对数据结果进行相关性分析。结果 本研究中掩饰性因子（Li）均小于8分,提示测试结果可信。分析表明,500例中国核电站操纵人员的办事风格因素平均得分为25.1±4.2,大多处于优良状态;不同的年龄、工龄、学历对办事风格心理因素的影响不同,但婚姻状况对其无明显影响;工龄、年龄较大组,学历较高组办事风格因素得分较低,而办事风格各因子中占高分组比例最大的为独立性因子。（P<0.05）结论 大多数中国核电站操纵人员的办事风格成熟稳重,其年龄、工龄、学历等对其均有一定影响。     

Radon measurement quality, how accurate is reasonable?

Until 2006, continuous radon monitoring devices, CR, could either be calibrated by reference to known quantities or by internal adjustments and or alignments. In 2007, a policy was advanced by the National Radon Safety Board and the National Environmental Health Association mandating internal adjustment and or alignment. Further, calibrations could only be performed by radon chamber persons authorized by the specific device manufacturer, which was a process that was impossible for many chamber operators to achieve. The paper serves to examine the technical validity for routine internal adjustments to Honeywell and Sun Nuclear (Sun Nuclear Corporation, 425A Pineda Court, Melbourne, FL 32940-7508) devices in contrast to the clear market controlling advantages of the policy. The purpose for making radon measurements is to assess risk. Comparing the uncertainties associated with risk to counting uncertainties of Honeywell and Sun Nuclear CR devices, less than 1% of model 1027 devices would have a calibration error exceeding 25%, and those devices, at this Radon Measurement Proficiency limit, would produce results that were more precise and accurate than the radon risk uncertainty. This was true for CR devices that have not been internally adjusted nor corrected in any way. It was concluded that internal adjustment or alignment better supported business principles than science.     

HSE's Safety Assessment Principles for radiation protection.

The Health and Safety Executive (HSE) published its revised Safety Assessment Principles for Nuclear Facilities (SAPs) in December 2006. The SAPs are primarily intended for use by HSE's inspectors when judging the adequacy of safety cases for nuclear facilities. The revised SAPs refer in part to HSE's expectations relating to the technical discipline of radiation protection. The purpose of this paper is to describe for the benefit of a wider audience HSE's reasoning behind the final published SAPs and to set out the purpose of each specific radiation protection (RP) principle. The paper also discusses principles in other sections of the SAPs which are relevant to radiation protection. The paper notes that the SAPs should be viewed as a reflection of good practice in relation to nuclear facilities in the context of interpreting relevant parts of primary legislation such as the Nuclear Installations Act 1965.     

Radiation protection performance indicators at the Nuclear Power Plant Krsko

Nuclear power plant safety performance indicators are developed "by nuclear operating organisations to monitor their own performance and progress, to set their own challenging goals for improvement, and to gain additional perspective on performance relative to that of other plants". In addition, performance indicators are widely used by regulatory authorities although the use is not harmonised. Two basic performance indicators related to good radiation protection practice are collective radiation exposure and volume of low-level radioactive waste. In 2000, Nuclear Power Plant Krsko, a Westinghouse pressurised water reactor with electrical output 700 MW, finished an extensive modernisation including the replacement of both steam generators. While the annual volume of low-level radioactive waste does not show a specific trend related to modernisation, the annual collective dose reached maximum, i.e. 2.60 man Sv, and dropped to 1.13 man Sv in 2001. During the replacement of the steam generators in 2000, the dose associated with this activity was 1.48 man Sv. The annual doses in 2002 and 2003 were 0.53 and 0.80 man Sv, respectively, nearing thus the goal set by the US Institute of Nuclear Power Operators, which is 0.65 man Sv. Therefore, inasmuch as collective dose as the radiation protection performance indicator are concerned, the modernisation of the Krsko nuclear power plant was a success.     

Comparison of retrospective luminescence dosimetry with computational modeling in two highly contaminated settlements downwind of the Chernobyl NPP

The cumulative absorbed dose in bricks collected from six buildings in two heavily contaminated settlements (137Cs > 2,000 kBq m(-2)) located downwind of the Chernobyl Nuclear Power Plant was determined using luminescence techniques by six laboratories. The settlements, Vesnianoje in Ukraine and Zaborie in Russia, are located in, respectively, proximal and distal locations relative to the Chernobyl Nuclear Power Plant. The luminescence determinations of cumulative dose in brick, after subtraction of the natural background dose, were translated to absorbed dose in air at a Reference Location using conversion factors derived from Monte Carlo simulations of photon transport. The simulations employed source distributions inferred from contemporary soil contamination data and also took into account heterogeneity of fallout deposition. This translation enables the luminescence determinations to be compared directly with values of cumulative absorbed dose obtained by computational modeling and also other dose reconstruction methods. For each sampled location the cumulative dose was calculated using three deterministic models, two of which are based on the attenuation of dose-rate with migration of radionuclides in soil and the third on historic instrumental gamma dose-rate data. The results of the comparison of the two methods indicate overall agreement within margins of +/-25%. The methodology developed is generally applicable and adaptable to areas contaminated by much lower levels of radioactive fallout in which brick buildings are found.     

Results of inspection and cleaning of two radionuclide air-sampling systems based on the requirements of ANSI/HPS N13.1-1999

The Pacific Northwest National Laboratory inspected and cleaned two radionuclide air-sampling systems that continuously monitor radioactive air emissions from research and development facilities. The inspection and cleaning was performed to evaluate effective methods and potential cost impacts of maintenance requirements in the revised American National Standard Institute standard Sampling and Monitoring Releases of Airborne Radioactive Substances from the Stacks and Ducts of Nuclear Facilities. The standard requires at least annual inspections of sampling systems followed by cleaning if deposits are visible. During 2001 and 2002, inspections were performed leaving the sampling systems in place and inserting videoscope cables into different access points to allow viewing of the inside and outside of sampling manifolds and transport lines. Cleaning was performed on one of the systems by disconnecting and extracting the sampling manifold, then washing it with de-ionized water and scrub brushes. The wash water was analyzed for radioactivity and solids. Results of the inspection showed greater deposition in one of the systems than would be expected by a High Efficiency Particulate Air (HEPA) filtered exhaust stream, possibly due to accumulation of dust from a short period when unfiltered air was exhausted from construction areas. The second system was also downstream of HEPA filters and appeared much cleaner. The videoscope was a useful and cost-effective tool and provided a better view than could be obtained with the naked eye. However, because even small amounts of deposition were made visible with the videoscope, clarification is needed in defining when probe washing is merited, particularly in existing sampling systems whose design is not conducive to easy removal and cleaning.     

三门核电站宁海毗邻区域辐射水平本底调查

目的 了解三门核电站运行前宁海毗邻区域环境γ辐射剂量和环境介质的放射性水平,建立环境辐射本底基线数据。方法 采用碘化钠闪烁体探测法和热释光累积剂量法测定监测区域环境γ外照射剂量率和环境辐射累积剂量,采用低本底α/β探测装置测定监测区域水源水总α和总β辐射剂量,食品样品放射性核素采用γ能谱仪测定。结果 监测区域居民人均年有效剂量为0.928 mSv;原野γ外照射剂量率为(98.32±21.08) nGy/h;环境辐射年累积剂量为(1.040±0.044) mSv。原野γ外照射剂量率和环境辐射累积剂量均有季节性差异。20 km范围内监测区域环境γ外照射剂量率和环境辐射累积剂量与10 km和30 km范围的测量结果差异无统计学意义。食品样品放射性核素检出值均远小于国家标准,水源水样品总放射性指标符合国家饮用水标准。结论 三门核电站宁海毗邻区域放射性本底在正常水平范围内,环境放射性本底有季节性差异。本次调查为三门核电站运行前宁海毗邻区域放射性本底建立了基线数据,⁹⁰Sr、¹³⁷Cs、¹³¹I等人工放射性核素是今后食品样品监测的重点。