北京地区大气中7Be、137Cs和131I活度浓度分布规律初步研究

介绍了全面禁止核试验条约（CTBT）国际监测系统（IMS）北京核素台站和北京放射性核素实验室的大气气溶胶取样和测量过程;对核素台站和放射性核素实验室的大气气溶胶的长期监测数据进行了统计分析,得到了⁷Be、¹³⁷Cs和¹³¹I活度浓度的分布特点和规律,为深入研究大气中相关放射性核素浓度分布规律奠定了基础。     

福岛核事故应急监测气溶胶样品γ核素分析结果的修正

本文通过对福岛核事故期间应急监测工作的总结,发现了应急监测期间气溶胶样品γ核素分析结果需修正。样品中短半衰期核素,特别是采样时间和测量时间较长的样品需进行衰变修正,给出了采样、放置、测量时间衰变修正因子。在分析气溶胶样品中放射性核素活度浓度时,需考虑滤膜收集效率修正,文中采用双滤膜法给出了两种常用滤膜的收集效率。针对气溶胶中¹³⁷Cs的分析,介绍了有干扰峰的γ能谱解谱方法,并提出了分析气溶胶样品时降低干扰的措施。本文对气溶胶样品γ核素分析结果的修正方法,可为全国性核事故应急监测提供参考。     

北京市气溶胶放射性核素分析(2013—2016)

利用中国锦屏地下实验室(CJPL)低本底γ谱仪对北京地区近4年34组气溶胶样品中长寿命放射性核素进行研究。发现气溶胶样品中含有²³⁸U、²²⁶Ra、²¹⁰Pb、²³²Th、²²⁸Ra、 ⁴⁰K、⁷Be、¹³⁷Cs,其活度浓度均值分别为17.47 μBq·m^-3、21.19 μBq·m^-3、2.39 mBq·m^-3、11.12 μBq·m^-3、14.43 μBq·m^-3、226.64 μBq·m^-3、6.98 mBq·m^-3、2.36 μBq·m^-3,且均在本底范围之内。同时,放射性核素活度浓度与环境参数存在相关性,⁷Be、⁴⁰K、¹³⁷Cs、²²⁶Ra均与季节负相关,²¹⁰Pb与季节正相关;⁴⁰K与空气质量指数(AQI)正相关。     

茄子对干沉积90Sr、137Cs的截获和易位行为研究

开展农作物对干沉积放射性气溶胶的截获和易位行为研究,对于公众辐射剂量估算以及旨在降低农产品放射性污染应对措施的有效性评估至关重要。选取我国代表性果菜类作物——茄子作为研究对象,在实验室开展了典型裂变产物⁹⁰Sr、¹³⁷Cs在茄子不同生长阶段的截获和易位行为研究。结果表明,试验植物对放射性核素的截获份额和易位因子随植株生长时间的延长而增大。开花期茄子对⁹⁰Sr、¹³⁷Cs的截获份额分别为0.14、0.21,结果期茄子对⁹⁰Sr、¹³⁷Cs的截获份额分别为0.17、0.26;开花期茄子对⁹⁰Sr、¹³⁷Cs的易位因子分别为1.6、4.7,结果期茄子对⁹⁰Sr、¹³⁷Cs的易位因子分别为2.3、5.9。就不同核素而言,不同生长阶段试验植物对¹³⁷Cs的截获份额和易位因子均高于⁹⁰Sr。     

压水堆核电厂气态流出物环境累积效应研究

核电厂运行寿期内放射性气载流出物通过烟囱向环境排放，其中部分放射性物质会沉降并在环境中累积。为评估其累积效应，本文选取³H、¹⁴C和以气溶胶形式存在的⁸⁸Kr/⁸⁸Rb、⁶⁰Co、¹³¹I和¹³⁷Cs作为代表性核素，采用³H、¹⁴C平衡模型和气溶胶迁移扩散模型，分析了核电厂运行寿期内各核素的环境累积活度浓度。分析结果表明：代表性核素显示出了环境累积效应，绝大多数代表性核素的环境累积活度浓度远小于0.1 Bq/kg，但³H和¹⁴C的环境累积活度浓度略高，分别达2.51 Bq/kg和2.35 Bq/kg；各核素环境累积活度浓度预测结果远低于EPR-RSR给出的相应限值，不会对土地再利用造成影响；以气溶胶形式存在的放射性核素的环境浓度表现出较明显的累积增长趋势，增长趋势与半衰期和放射性核素在环境中的迁移行为相关。根据研究结果，对我国核电厂环境影响评价中典型核素的环境累积效应预测和环境监测提出了建议。     

安徽地区气溶胶中137Cs活度浓度监测

利用超大流量气溶胶采样器和γ谱仪,对安徽三个点位气溶胶中人工放射性核素137 Cs活度浓度进行了为期两年的采样监测,共六次检出超过探测限的¹³⁷ Cs,活度浓度为1.4～6.5μBq/m³。结合国家辐射环境监测网现有数据,对安徽地区气溶胶中¹³⁷Cs活度浓度与季节、空气条件关系进行了分析,为深入研究大气中相关放射性核素浓度分布规律奠定了基础。     

秦山核电基地外围环境放射性水平20年监测结果

浙江省辐射环境监测站对秦山核电基地外围环境放射性水平的20年监督性监测结果表明,秦山核电基地外围环境 γ 辐射剂量率,气溶胶中总α、总β、⁴⁰K、¹³⁷Cs的活度浓度,沉降物中总β日沉降量,空气中¹⁴CO₂活度浓度,陆地淡水（饮用水、湖塘水、井水）中总α、总β、⁹⁰Sr、¹³⁷Cs的活度浓度,土壤中 γ 核素²³⁸U、²³²Th、²²⁶Ra、¹³⁷Cs的比活度,生物样品中放射性核素⁴⁰K、¹³⁷Cs、⁹⁰Sr及¹⁴C的比活度,均未发现异常,与对照点监测值和运行前本底调查值相比,属同一水平。空气、雨水、地表水、饮用水、排放口海水和陆生植物样品中³H活度浓度均高于相应对照点监测值,部分介质中³H活度浓度远高于基地运行前相应的本底。说明秦山核电基地20年的运行,特别是秦山三期重水堆运行之后,其外围环境已受到基地流出物中³H排放的影响。     

CTBT气溶胶γ能谱的能量漂移校正方法

CTBT放射性核素台站气溶胶样品通常采用HPGe γ谱仪系统测量，能量刻度是核素识别的关键。针对放射性核素台站气溶胶γ能谱存在的能量漂移问题，提出了一种基于²¹²Pb、²¹²Bi、²⁰⁸Tl、²¹⁰Pb、⁴⁰K和⁷Be等天然放射性核素γ射线的能量漂移校正方法。测试结果表明，该能量漂移校正方法能有效校正能谱中γ峰能量偏差。     

在线式放射性液态流出物监测仪研制

本文针对核设施中液态流出物关键伽马核素⁶⁰Co、¹³⁷Cs的测量,采用自主专利等多项技术设计样机,基于NaI(Sodium Iodide)闪烁体探测器的自动核素识别,开发了探测灵敏度更好、质量更轻便且满足通用的建筑承载能力的在线式液态流出物监测装置。设计加工集成的样机经过能量刻度、效率刻度、感兴趣区自动划分核素识别测试,并通过国家一级计量站校准测试,经过超过500多小时实验,其性能稳定可靠,具有核素识别能力,测试显示⁶⁰Co、¹³⁷Cs探测限小于0.088 Bq/L。对比国内传统监测技术,质量减轻接近1个数量级,探测灵敏度提升超过2个数量级,监测技术及其样机从技术能力而言也适用于饮用水伽马关键核素活度浓度监测。     

便携式γ谱仪对137Cs、131I液样探测效率的刻度

便携式γ谱仪主要用于主冷却剂水样中典型核素的现场辅助识别及其活度浓度的测量分析。为确定典型核素特征峰净面积和水样中该核素活度浓度的关系，必须进行源峰效率刻度。本文通过测量¹³³Ba、¹³⁷Cs、⁶⁰Co 3种核素的混合溶液得到效率刻度曲线，然后对不同活度浓度的¹³⁷Cs标准溶液、¹³¹I标准模拟溶液进行测量。结果表明，谱仪均能正确识别¹³⁷Cs、¹³¹I核素，活度浓度测量的相对误差均<10%，初步满足元件破损监测精度和灵敏度的需求。     

放射性核素从废物体中向外释放行为初步研究

以去离子水为初始释放环境,考察了1年释放周期内,两类典型低、中水平放射性废物固化体在被水完全浸泡情景下,3种关键核素⁶⁰Co、¹³⁷Cs、⁹⁰Sr的向外释放行为。使用平均有效扩散系数作为表征参数。多个样品的测试结果表明：3种核素向外释放表现出规律性的趋势,即¹³⁷Cs最快,⁶⁰Co最慢, ⁹⁰Sr相比居中。对于不同的核素,起始活度对释放行为的影响是不同的。借助SEM探讨了废物体微观结构对核素释放的影响。     

Environment Accumulation Effect from Gaseous Effluent of Pressurized Water Reactor Plant

During the operation of nuclear power plant (NPP), gaseous radioactive effluent discharges into the environment via the stack, and some of them will deposit and accumulate in the environment. In this paper, ³H, ¹⁴C and ⁸⁸Kr/⁸⁸Rb, ⁶⁰Co, ¹³¹I and ¹³⁷Cs were selected as the representative nuclides to analyze their environment accumulation effect. The result reveals the environment accumulation effect of representative nuclide. Accumulative concentrations of most nuclides are less than 0.1 Bq/kg, while those of ³H and ¹⁴C are slightly high, which are 2.51 Bq/kg and 2.35 Bq/kg respectively. Accumulative concentration of individual nuclide is still far less than relative criteria in EPR-RSR. Therefore accumulation of these nuclides in the local environment will not affect the land reuse. The environmental concentration of aerosols shows a clear cumulative growth trend which is relevant to half-life of nuclides and their migration in the environment media. Based on this study, some recommendations are put forward for the prediction of environment accumulation effects of typical nuclide and environmental monitoring for the environmental impact assessment in China.     

A new back-end cycle strategy for enhancing separation, transmutation and utilization of materials (Adv.-ORIENT cycle)

To minimize the ecological burden originating in nuclear fuel recycling, a new R&D strategy, the Adv.-ORIENT (Advanced Optimization by Recycling Instructive Elements) cycle was set forth. In this context, mutual separation of f-elements, such as minor actinide (MA)/lanthanide (Ln) and Am/Cm, are essential to enhance the MA (particularly ²⁴¹Am) burning. Isotope separation before transmutation is also inevitably required in the case of some long-lived fission products (LLFPs) like ¹²⁶Sn, ¹³⁵Cs, etc. The separation and utilization of rare metal fission products (RMFPs: Ru, Rh, Pd, Tc, Se, Te, etc.) are offering a new direction in the partitioning and transmutation (P&T) field. ⁹⁹Tc and ¹⁰⁶Ru, well-known interfering nuclides in reprocessing, should be removed prior to the actinide stream. Separation of exothermic nuclides ⁹⁰Sr, ¹³⁷Cs as well as MA will significantly help to mitigate the repository tasks.

A key separation tool is ion exchange chromatography (IXC) by a tertiary pyridine resin having soft donor nitrogen atoms. This method has provided individual recovery of pure Am and Cm products with a Pu/U/Np fraction from irradiated fuel in just a 3-step separation. A catalytic electrolytic extraction (CEE) method by Pd_adatom has been employed to separate, purify and fabricate RMFP catalysts. Differently functioned ion exchangers, e.g., ammonium molybdophosphate (AMP), have been investigated for the separation of Cs⁺. Theoretical and laboratory studies on the isotope separation of LLFPs were begun for ⁷⁹Se, ¹²⁶Sn and ¹³⁵Cs.     

Neutron economy and nuclear data for transmutation of long-lived fission products

In the study of Self-Consistent Nuclear Energy System, the following 29 long-lived fission products (LLFPs) have been selected to be transmuted into stable or short-lived nuclides: ¹⁰⁶Ru, ¹⁰²Rh, ¹⁰⁹Cd, ¹²⁵Sb, ¹³⁴Cs, ^146,147Pm, ^154,155Eu, ¹⁷¹Tm, ⁸⁵Kr, ⁹⁰Sr, ^93mNb, ^113mCd, ^121mSn, ¹³⁷Cs, ¹⁵¹Sm, ¹⁵²Eu, ^108mAg, ¹⁵⁸Tb, ^166mHo, ⁷⁹Se, ⁹³Zr, ⁹⁴Nb, ⁹⁹Tc, ¹⁰⁷Pd, ¹²⁶Sn, ¹²⁹I, ¹³⁵Cs. In the present study, the number of neutrons necessary for the transmutation of the 29 LLFPs with an FBR was evaluated, and the present status of the (n, γ) and (n,2n) cross section data of the 29 LLFPs in JENDL-3.2 and ENDF/B-VI was investigated. The main results of the present study are as follows: (1)only 0.25 neutron per fission is necessary for the transmutation of the 29 LLFPs with isotopic separation, whereas 6.8 neutrons are necessary with chemical separation, (2)the accuracy of the cross sections is 30 to 100% except for the (n, γ) cross sections of limited nuclides in limited incident neutron energy regions.     

海水中~(131)I的快速检测技术

日本福岛核事故发生以后,对海洋环境中关键放射性核素的快速检测技术提出了更高的要求。人工放射性核素~(131)I在核反应裂变产物中活度相对较高且半衰期短,是用来快速评价核污染的关键性核素之一。本工作从亚铁氰化钾、硝酸铜及硝酸银为原料出发,制备出亚铁氰化铜和亚铁氰化银混合(CuFC/AgFC)吸附材料并分散于聚丙烯纤维富集柱上,来实现水环境中~(131)I现场快速富集。通过室内模拟实验发现:在流速为6.25L/min,~(131)I在海水中I~-初始浓度为24μmol/L时,单次吸附效率即可达到50%以上;而当海水中I~-初始浓度为4μmol/L时,一定体积的海水在连续循环8次后(CuFC/AgFC)聚丙烯纤维富集柱吸附效率达到100%。本方法制源时间约40min,测样时间约12~24h,故最快可在30h内完成海水中~(131)I的分析。本方法的检测限与分析周期均低于目前GB/T 13272-1991水中~(131)I的分析标准,极大地提高了~(131)I的分析时间。除此之外,该法可以同时分析海水中的~(137) Cs(~(134) Cs),有望作为淡水和近岸环境中常规监测和应急时对关键核素~(131)I和~(137) Cs(~(134) Cs)进行快速测定的备选方法之一。     

环境水体中~(90)Sr和~(137)Cs的监测方法

以国家标准为基础,对环境水体中~(90)Sr和~(137)Cs的监测方法进行了技术改进:增大采样量(50~100L),选择高效沉淀剂和低水平探测器。采用改进后的方法测定了50~100L水中~(90)Sr和~(137)Cs,结果显示:~(90)Sr和~(137)Cs的浓集效率分别为(91.3±2.8)%和(97.2±1.4)%;~(90)Sr的全程回收率为81.5%±2.8%;~(90)Sr和~(137)Cs的探测下限分别为8.6×10~(-4) Bq/L和9.8×10~(-4) Bq/L。50L水中~(90)Sr的比对结果显示,4家实验室测定值与标称值的相对偏差均小于11%。以上结果表明,该方法适用于环境水中微量~(90)Sr和~(137)Cs的监测,可满足环境本底调查和环境监测的要求。     

Research of Radioactive Source Term Calculation Model and Application in LOCA for PWR

According to the mechanism of the generation and reduction of the nuclide in the process of migration and release from the core to the containment and the environment after the pressurized water reactor (PWR) loss of coolant accident (LOCA), the calculation model of radioactive source term for LOCA was established. The comparative analysis of model calculation results was carried out. Finally, the model was applied to the source term analysis for the third generation PWR LOCA. The results show that the relative deviation between the calculation results of the model and TACTⅢ code is within ±0.05%, and the relative deviation between the iodine calculation results of the model and TITAN5 code is within ±0.5%, so the model calculation is accurate. For various nuclear motor types of PWRs, the removal mechanism and removal rate of nuclide in the containment are different, resulting in different I and Cs radioactivity release curves. The cumulative radioactivity of ¹³¹I, ¹³⁴Cs, ¹³⁶Cs and ¹³⁷Cs released into the environment within 30 d gradually increases. The established model is highly versatile, which is based on the complete nuclide decay chain, considering the contribution of the precursor nuclides decay to the daughter nuclides, and the effective removal process of elemental iodine by spraying or natural removal.     

~(60)Co放射源运输容器屏蔽性能检测

工业及医疗用放射源主要包括60 Co、137 Cs、131I、32P、153Sm、99 Mo、90Sr、89Sr等核素,射线形式有α、β、γ、中子等。本文针对运输活动中γ辐射,使用现有的60 Co放射源运输容器,开展辐射屏蔽性能检测技术研究。通过模拟计算和实验测量,得到运输容器最大装载活动情况下外部辐射水平,并对计算和实验结果进行了比较。针对放射源在屏蔽容器中安放位置发生偏移和放射源在容器中安放方式不同对容器外部的辐射水平影响进行了相关研究。研究结果可对今后完善放射性物质运输容器的辐射屏蔽性能检测提供一定的借鉴。