内陆核电厂排放氚的辐射环境影响评价

介绍了核电厂正常运行时以气态和液态形式排放的氚在环境中的迁移转化模型,提出内陆核电厂排放氚的辐射环境影响评价的方法,模型中考虑了氚的两种化学形态,即氚化水(HTO)和有机结合氚(OBT),同时计算了氚通过饮水、食入、吸入、皮肤吸收等途径对公众造成的辐射剂量。采用该模型估算了内陆核电厂液态排放氚在环境中的传输以及对公众受照剂量的贡献,基于IAEA TRS 472号报告提供的参数,在保守的大气弥散和水弥散条件下,内陆核电厂排放氚对公众造成的年辐射剂量为5.16μSv,其中核电厂液态排放氚对公众造成的辐射剂量约占四分之三,气态排放氚对公众造成的辐射剂量仅占四分之一。在氚的两种形态中,HTO是对公众造成辐射的主要化学形态,对公众造成的辐射剂量份额占80%以上。因此,在内陆核电厂排放氚的公众剂量评价时,应多关注液态氚排放途径。     

多堆事故近场区辐射剂量评价方法初步研究

多堆事故源项具有多点同时释放、直接照射更强、各厂房屏蔽效应及反射效应交织、放射性物质浓度计算更加复杂的特点。现有的辐射剂量评价方法及系统难以满足多堆事故近场区应急评估需求。研究表明近场区小尺度风场和大气扩散对应急人员受到的烟羽照射剂量影响较大,大气扩散模型不能忽略附近复杂地形、建筑物等因素影响。对我国主要核电基地反应堆分布情况及场址特点进行了分析研究,选取CFD作为多堆场址近场区流场计算模拟手段。"保守法"用于多堆剂量场叠加计算快捷,易于操作;"现实法"计算量相对较大,但精度更高。应根据应急需要,选取合理的剂量叠加计算方法。     

人及动植物的辐射剂量评价模式

随着核能工业和核技术应用的发展，人们对放射性物质向环境排放的管理越来越重视，要求对处置放射性废物过程中可能对人和野生动植物产生的影响进行评价。要对释放到环境中的放射性所致辐照剂量进行评价，一定型式的环境评价模式是必不可少的。本文综合近年来辐射防护和放射生态学研究的进展，对建立辐射剂量评价模式的基本要求和未来研究重点进行了初步归纳。     

秦山核电基地氚排放所致周围公众内照射剂量评价

统计了2014—2016年秦山核电基地周围居民点环境介质中的氚活度浓度监测结果,基于统计的环境监测数据评价了秦山核电基地近几年氚排放所致周围公众的辐射剂量。评价结果显示近几年秦山核电基地氚排放所致西北西方位2.4 km处的秦联居民组婴儿、幼儿、少年和成人4个年龄组公众的年平均有效剂量分别为0.59、1.35、1.18和0.92 μSv/a,远小于《核动力厂环境辐射防护规定》(GB 6249—2011)中规定的核动力堆释放的放射性物质对公众造成的有效剂量0.25 mSv/a的管理目标值。可见,秦山核电基地氚排放稳定、受控,对公众造成的辐射剂量很小,对环境和公众的影响可接受。     

人及动植物的辐射剂量评价模式

随着核能工业和核技术应用的发展 ,人们对放射性物质向环境排放的管理越来越重视 ,要求对处置放射性废物过程中可能对人和野生动植物产生的影响进行评价。要对释放到环境中的放射性所致辐照剂量进行评价 ,一定型式的环境评价模式是必不可少的。本文综合近年来辐射防护和放射生态学研究的进展 ,对建立辐射剂量评价模式的基本要求和未来研究重点进行了初步归纳。     

人及动植物的辐射剂量评价模式

随着核能工业和核技术应用的发展，人们对放射性物质向环境排放的管理越来越重视，要求对处置放射性废物过程中可能对人和野生动植物产生的影响进行评价。要对释放到环境中的放射性所致辐照剂量进行评价，一定形式的环境评价模式是必不可少的。本文综合近年来辐射防护和放射生态学研究的进展，对建立辐射剂量评价模式的基本要求和未来研究重点进行了初步归纳。     

中国东北某核电基地流出物排放致公众剂量评价(2013—2020年)

本文介绍了气载流出物与液态流出物排放所致公众剂量的计算模式与方法，分析了2013—2020年中国东北某运行核电厂流出物排放对周围公众造成的最大个人有效剂量、关键居民组、关键照射途径、关键核素与核电厂80 km范围内集体有效剂量以及各年度流出物归一化排放量，并与相关标准要求进行了对比。结果表明：通过对各年度《辽宁红沿河核电厂流出物与环境监测评价年报》和《辽宁红沿河核电厂辐射剂量影响评价报告》的数据分析及核算，该核电厂流出物排放致公众剂量远低于国家标准、环境影响报告书及生态环境部批复的年排放限值，各年度流出物排放对周围公众造成的影响很小。     

气态氚排放后HTO和OBT在环境介质中的估算

本文介绍了长期大气释放下氚的剂量评价模型——比活度模型。该模型考虑了氚的两种形态HTO和OBT,对长期大气释放下氚在环境介质中的迁移行为,氚浓度的估算进行了描述。     

现场环境氡子体未结合态份额测量及剂量评价

氡子体未结合态份额直接影响环境中氡暴露剂量。为了弄清楚现场环境氡子体未结合态份额,准确评价氡暴露剂量,利用累积式氡子体未结合态份额测量装置对环境中氡子体未结合态份额进行了现场测量,对不同环境氡暴露剂量和未结合态氡子体的影响进行了评价。研究表明,尽管不同环境氡子体浓度有较大差别,室内外氡子体未结合态份额差别不是太明显,室内外环境氡子体未结合态份额变化范围9.27%～16.87%,未结合态氡子体对氡子体暴露有效剂量贡献的份额在30.22%～46.24%变化,矿山环境氡子体未结合态份额和剂量贡献份额明显高于室内环境。     

华龙一号核电厂公众辐射剂量优化设计目标值研究

基于我国新建三代压水堆核电机组华龙一号运行状态下的流出物设计与现实排放源项,结合机型的排放特点、沿海与内陆厂址的不同环境和气象等条件,对新建核电厂公众剂量优化设计目标值进行了研究。研究结果表明,在我国华龙一号的设计方案下,对于滨海厂址条件所能够达到的公众剂量优化设计目标值可以达到与欧美国家体系相当的水平。但由于厂址环境条件的差异,对内陆核电厂还需要结合工艺系统的改进开展进一步深入研究工作。对流出物中氚和C-14的排放还需要进一步开展经验反馈积累,在此基础上给出更符合未来运行状态的辐射剂量评价结果。本研究还对华龙一号后续的排放源项和评价方法等方面给出了建议,对进一步加强华龙一号的环境友好性和先进性具有积极作用。     

ICRP Publication 115. Lung cancer risk from radon and progeny and statement on radon

Recent epidemiological studies of the association between lung cancer and exposure to radon and its decay products are reviewed. Particular emphasis is given to pooled case-control studies of residential exposures, and to cohorts of underground miners exposed to relatively low levels of radon. The residential and miner epidemiological studies provide consistent estimates of the risk of lung cancer, with significant associations observed at average annual concentrations of approximately 200 Bq/m3 and cumulative occupational levels of approximately 50 working level months (WLM), respectively. Based on recent results from combined analyses of epidemiological studies of miners, a lifetime excess absolute risk of 5 × 10?? per WLM [14 × 10?? per (mJh/m3)] should now be used as the nominal probability coefficient for radon- and radon-progeny-induced lung cancer, replacing the previous Publication 65 (ICRP, 1993) value of 2.8 × 10?? per WLM [8 × 10?? per (mJh/m3)]. Current knowledge of radon-associated risks for organs other than the lungs does not justify the selection of a detriment coefficient different from the fatality coefficient for radon-induced lung cancer. Publication 65 (ICRP, 2003) recommended that doses from radon and its progeny should be calculated using a dose conversion convention based on epidemiological data. It is now concluded that radon and its progeny should be treated in the same way as other radionuclides within the ICRP system of protection; that is, doses from radon and its progeny should be calculated using ICRP biokinetic and dosimetric models. ICRP will provide dose coefficients per unit exposure to radon and its progeny for different reference conditions of domestic and occupational exposure, with specified equilibrium factors and aerosol characteristics.     

北京市环境水中锶-90活度浓度分析

为了测量北京市环境水中⁹⁰Sr的活度浓度,分析其长期趋势及在全国的水平,参照《水和生物样品灰中锶-90的放射化学分析方法》(HJ 815—2016),分析北京市12个环境点位中⁹⁰Sr的活度浓度。结果显示,2019年北京市环境地表水中⁹⁰Sr活度浓度为(4.46±1.51)mBq/L,范围(1.44~7.56)mBq/L,其中河系水(5.01±1.45)mBq/L,湖库水(4.00±1.45)mBq/L,地下水(2.11±0.12)mBq/L。得出结论:北京市环境水中⁹⁰Sr含量为低水平;与历年相比,处于正常涨落范围之内;与全国其他地区相比,处于中间水平。水中⁹⁰Sr所致成人年均摄入量最大为3.66 Bq/a,待积有效剂量最大为0.10 μSv/a,均远远小于国家标准限值。     

2013—2018年山西省放射性废物库库区环境γ辐射水平监测

为了进一步加强对放射性废物库的安全管理,确保辐射环境安全,对2013—2018年山西省放射性废物库库区环境γ辐射剂量率的监测结果进行了分析。结果表明,库区环境γ辐射水平满足《核技术利用放射性废物库选址、设计与建造技术要求(试行)》中有关库房内源坑盖板上方0.5 m处γ辐射剂量率不超过20 μGy／h、源库墙外表面0.2 m处γ辐射剂量率不超过2.5 μGy／h的规定要求,各年度间环境电离辐射水平处于本底涨落范围内,未对周围环境产生辐射影响,辐射环境质量总体良好。此外,健全的库区安全防范也为促进我省核技术利用和安全、健康、可持续发展提供了坚强保障。     

用公众健康危害指标对我国燃煤电厂气载释放物的环境危害评价

本文在详细调查我国燃煤电厂除尘器类型及除尘效率等基本状况的基础上，利用公众健康危害评价方法评价了我国燃煤电厂载释放的非放化学污染物和放射性物质所致的公众健康危害。计算结果表明我国燃煤电厂载释放物的危害主要是由其非放化学污染物产生的。     

Annealing of total dose damage: redistribution of interface state density on [100], [110] and [111] orientation silicon

The annealing of interface states after an X-ray dose of 10 Mrad (SiO/sub 2/) under 1-MV/cm bias is studied on [100], [110], and [111] silicon. During annealing the bias is 1 MV/cm. Annealing times range from under an hour to hundreds of hours, and the temperature ranges from 75 to 175 degrees C. Using charge pumping, the energy distribution of interface states within the bandgap is determined. After annealing, the shape of the interface-state density curve implies that one or more defects other than P/sub b0/ and P/sub b1/ are present. Comparison of the interface-state density curves before and after annealing shows that a redistribution of interface-state density occurs over a large portion of the time-temperature range studied. The density near 0.4 eV above the valence band decreases and the density near 0.7 eV increases although the average density does not significantly change. Based upon the time scale and activation energy of the redistribution, a model is proposed in which the rate-limiting step is water diffusion within the gate oxide to the interface. This model provides a framework for a transformation among interface defects that accounts for the observed redistribution. Further tests for this model are discussed.<>     

Neutron yields from 155 MeV/nucleon carbon and helium stopping in aluminum

Neutron fluences have been measured from 155 MeV/nucleon 4He and 12C ions stopping in an Al target at laboratory angles between 10 and 160 deg. The resultant spectra were integrated over angle and energy above 10 MeV to produce total neutron yields. Comparison of the two systems shows that approximately two times as many neutrons are produced from 155 MeV/nucleon 4He stopping in Al and 155 MeV/nucleon 12C stopping in Al. Using an energy-dependent geometric cross-section formula to calculate the expected number of primary nuclear interactions shows that the 12C + Al system has, within uncertainties, the same number of neutrons per interaction (0.99 +/- 0.03) as does the 4He + Al system (1.02 +/- 0.04), despite the fact that 12C has three times as many neutrons as does 4He. Energy and angular distributions for both systems are also reported. No major differences can be seen between the two systems in those distributions, except for the overall magnitude. Where possible, the 4He + Al spectra are compared with previously measured spectra from 160 and 177.5 MeV/nucleon 4He interactions in a variety of stopping targets. The reported spectra are consistent with previously measured spectra. The data were acquired to provide data applicable to problems dealing with the determination of the radiation risk to humans engaged in long-term missions in space; however, the data are also of interest for issues related to the determination of the radiation environment in high-altitude flight, with shielding at high-energy heavy-ion accelerators and with doses delivered outside tumor sites treated with high-energy hadronic beams.     

基于CFD方法的核设施气载流出物取样代表性研究

核设施气载流出物取样代表性的优劣,决定着对环境监测和辐射安全评价的准确性。应用计算流体力学(Computational Fluid Dynamics,CFD)方法,根据新版ISO 2889标准《核设施的烟道和通风管道中的放射性物质取样》中对取样位置的要求,对某核设施排气系统的流场进行了数值模拟并分析了不同取样位置的取样代表性。指出现有取样位置选取不尽合理的结论,通过对模拟结果进行分析,确定了合理取样位置,从而可以有效地监测放射性气载流出物的核素活度浓度,为辐射环境影响评价提供科学数据支持。     

PIXE as a complement to trace metal analysis of sediments by ICP-OES

The adverse effects of metal contamination in sediments require methods that can quickly and accurately assess the extent of environmental pollution. Particle induced X-ray emission spectrometry (PIXE) is demonstrated to be a viable alternative to an established method, which consists of acid digestion and Inductively coupled plasma-optical emission spectrometry (ICP-OES) to measure trace metals in sediment. The analysis of trace metal composition by both techniques on a NIST Standard Reference Material mud gives results that are consistent with the certified values for fourteen measured metals, seven of which are common to both methods. A comparison study conducted on a sediment core from a freshwater lake with a known chromium contamination in Muskegon County, MI also shows a good correlation between the methods for transition metals of environmental interest over a wide range of metal concentrations. Total sample preparation and analysis time for the PIXE measurements is roughly one third that of acid digestion and ICP-OES. Also, the acid digestion step does not elute all the metal, while the nondestructive PIXE approach is a total metals analysis method. However the PIXE method generally has higher limits of detection for many environmental metal contaminants. By combining the two techniques, the acid digestion elution factor can be quantified by running PIXE on an original sample and on the residue resulting from acid digestion.     

核设施正常工况气载放射性排出物辐射后果计算程序比对

本文介绍了我国的核设施环境影响报告书主要编写单位在对某参考核设施正常工况下气态排出物辐射后果计算时程序比对的结果。尽管各编写单位使用的程序、模式和参数均有差异，但所计算的结果均在一个数量级的偏差范围内，这说明参加比对的各程序应用于基本平坦地形的厂址和此类（流出物中以８５Ｋｒ或惰性气体为主的）核设施在正常运行工况下的计算结果是基本合理的     

浙江省石煤开发利用对环境的放射性影响

本文报道了石煤开发利用中产生的对环境的放射性影响问题。石煤中U、~(226)Ra含量高,在其生产和利用过程中,如无任何控制措施,可以导致环境放射性污染。调查结果表明:浙江省石煤开发利用区土壤中~(238)U 和~(226)Ra 含量分别比对照区高2.4和2.1倍;陆地γ辐射水平比对照区高44%;石煤渣砖建房室内γ辐射剂量率比对照区高80%;石煤渣砖建房室内氡及其子体浓度最高分别可比一般砖建房高35和42倍,室内氡子体所致居民年附加有效剂量当量为41.2mSv;并导致钱塘江冰系某些局部江段中~(238)U 和~(226)Ra 浓度增加了一个数量级。