松针中组织自由水氚的测量

本文用生物样品与有机溶剂共沸蒸馏分离法对秦山核电厂附近秦山上松针中组织自由水氚进行测量。选择甲苯为共沸蒸馏溶剂。松针与甲苯共沸蒸馏,组织自由水回收率达90%。结果表明,松针中组织自由水氚浓度为1.8 Bq/L,与同期大气中氚化水蒸气(HTO)的浓度在同一水平。     

液体闪烁计数法测定生物样品中组织自由水氚

本文介绍生的样品有机溶剂共沸蒸馏－－液体闪烁计数测定组织自由水氚法，组织自由水回收率松针，大米为９０％；青菜，萝卜为９５％；牛奶为８５％；猪肉（精）为５２％。松针（鲜），青菜，萝卜，大米，猪肉（精）与牛奶组织自由水氚活度为分别为１．８，３．２，１．８，２．７，３．３，４．０Ｂｑ／Ｌ－Ｈ２Ｏ。     

环境样品中自由氚和组织结合氚的收集

本文介绍了所建立的环境样品中的自由氚和组织结合氚的分别采样装置和方法。对于样品中的自由氚,用低真空干燥回收法,回收率可达98％;对于样品中的组织结合氚,用连续加样催化氧化冷凝收集法,回收率为93％。两法都能一次收集足够制两个并行测量样的水量。     

尿中氚水和总氚的分析测定

用蒸馏 液闪法和氧化蒸馏 液闪法分别测量了氚污染人员尿中的氚水和总氚(氚水和有机氚)的浓度。根据72个高于本底水平的尿中氚水和总氚浓度分析结果比较,认为在氚内污染工作人员的尿中,有机氚与氚水的浓度比值为(5.4±3.7)%。     

土壤样品中氚水的测定

本文介绍了土壤中氚水的测定方法，主要包括真空解析与冷凝、制样和液闪测量等步骤。当分析１２０ｇ湿度为２０％的土壤时，方法回收率为９６．７％，探测下限为０．７０Ｂｑ／ｋｇ。     

低温解析-液闪法检测植物中氚含量

为评价涉氚活动中氚对环境的影响,建立了低温解析—液闪法检测核设施周围植物样品中氚含量的分析方法。该方法将核设施周围植物样品中组织自由水氚(TFWT)在110~120℃解析出来,用液闪计数仪测量其氚含量。该分析方法比传统分析方法缩短约120 min,对植物样中TFWT的平均回收率优于76%,能够满足涉氚场所植物中TFWT的快速分析。     

植物样全氚制样装置的研制与验证

介绍了一种自行研制的用于进行植物样品全氚测量的制样装置,该装置将传统的高温氧化方式与明火燃烧的方式相结合,一次能够处理10.00～15.00g植物鲜样,处理时间为2～3h,与传统的高温氧化法相比,处理时间短,与国外同类装置相比,样品处理量大。经过实验验证,收集的冷凝水不需要再进行后续处理,可以直接进行液闪测量。     

植物中组织自由水氚的测量方法

为评价核设施退役中氚对环境的影响,可监测退役前后植物中氚的活度变化来反映.文章设计加工1套用于植物组织自由水解析的低温真空解析系统,该系统对云南杉树叶样品的最佳解析时间定为5～6 h,此时20 g样品至少能解析水4～5 mL用于液闪测量,对树叶中组织自由水的平均回收率为61%.     

液体闪烁计数法测定共沸蒸馏生物样品气氚活度

本文介绍液体闪烁计数测定有机溶剂共沸蒸馏生物样品组织自由水氚的方法。实验测得甲苯共沸蒸馏新鲜松针、青菜、萝卜、、牛奶、猪肉（精）和大米组织自由水的回收率，分别为０．９０、０．９５、０．９５、０．８５、０．５２和０．９０以及组织自由水氚活度．每升样品水中分别为１．８、３．２、１．８、４．０、３．３和２．７Ｂｑ。     

我国部分地区食品氚的分布规律初探

调查了我国北京、兰州、上海和成都四个城市的食品氚浓度，其中食品的游离水氚（ＴＦＷＴ）和有机结合氚（ＯＢＴ）浓度的平均值分别为４．５６Ｂｑ·Ｌ＾－１和２９．５１Ｂｑ·Ｌ＾－１，食品ＯＢＴ与ＴＦＷＴ含量的比值（ＳＡＲ）为６．４７。食品ＯＢＴ浓度由北往南逐渐下降（Ｐ〈０．０５），与纬度呈高度线性关系。植物类食品的ＯＢＴ浓度较动物类食品高，且地面生长食品的ＯＢＴ浓度最高，灌溉类食品最低。     

Tritium dose criteria and radiological impact of a tritium plant

Radiation safetry criteria adopted in Russia (in the former USSR) distinguish five classes of tritium compounds. The lowest permissible tritium concentration in the air is set for insoluble tritium compounds (3.10⁵ times lower than that for HT). Russia's criteria for tritiated radioactive waste are outlined. It is explained why the tritium weighting factor of two is used as a basis for the tritium dose criteria development in this country. The ecological situation nearby a large tritium processing plant is considered. Amounts of tritiated waste produced at the plant, sources of tritium effluents, tritium content in the air, water, snow, soil and vegetation as well as HTO sorption parameters of various food products are reported. On the basis of HTO near-surface concentrations in the air and public doses measured 3 km away from the plant stack, the tritium dose factor was calculated.     

防氚高分子复合材料的制备及其性能

利用氯化聚乙烯、聚偏二氯乙烯(Polyvinylidene chloride,PVDC)、高密度聚乙烯等高分子材料复合防氚材料。采用渗透实验测量氚气渗透率;通过测量断裂强力和剥离力测量力学性能;通过测量浸泡化学试剂前后的溶失率、断裂强力下降率、剥离力下降率等表征材料的耐化学性能。结果表明,氚气在防氚高分子复合材料中的渗透率为3.44×10-10 m3/(m2?s);与PVC相比,氚气渗透率降低约70倍。PVDC薄膜复合后断裂强力提高约20倍,经纬向断裂强力为721 N。防氚高分子复合材料浸泡5种化学试剂后,最大溶失率为0.29%、断裂强力最大下降率为5.1%,其力学性能、耐化学性能均满足《防护服装酸碱类化学品防护服》(GB24540-2009)等相关标准的要求。     

Investigation on hydrogen absorption/desorption properties of as-cast La(1-x)MgxNi4.25Al0.75 (x =0.0, 0.1, 0.2, 0.3) alloys for tritium storage

La_((1-x))Mg_xNi_(4.25)Al_(0.75)(x = 0.0, 0.1, 0.2, 0.3)alloys for tritium storage were prepared by a method of electromagnetic induction melting. The crystal structure and hydrogen storage performance of the as-cast alloys were investigated. The results showed that a single phase of La Ni_4Al was in the alloys with x = 0.0 and 0.1 and that LaNi_4Al and second phase of(La,Mg)Ni)_3 and AlNi_3 were in the alloys with x = 0.2 and 0.3. On the other hand, the plateau pressures of P–C isotherms of the alloys were increased with the rise of the x value from 0.2 to 0.3 and the hydrogen storage capacity was obviously degraded simultaneously. It was found that the alloy had faster absorption kinetics as the proportion of Mg increased from 0.1 to 0.3.     

Enhanced tritium production for fusion reactors via3He(n,p)3 H in the heavy water moderator of a CANDU reactor

There is an increasing requirement for tritium to supply the fuel needs of current experimental fusion devices and in the initial startup of future power generating reactors. Tritium is produced in heavy water reactors through deuterium activation, but the total production capacity of Canadian operated CANDUs will fall short of future demands, during the period before and for some time after self-sufficient reactors become available. Consequently, methods of enhancing tritium generating rates warrant investigation. Herein we provide the results of an inquiry into the feasibility of enhancing tritium production levels through the activation of helium-3 following its external addition to the heavy water moderator system of a hypothetical 500–600 MWe CANDU reactor. The approach adopted involves simulation of the temporal evolution of the tritium activities, originating from²H(n,)³H and³He(n, p)³H, as described by a simple first order kinetic model. The results suggest that the frequent addition of helium-3 to the moderator water will enhance tritium production inventories. The enhancement factor is highly dependent upon the rate at which helium-3 irretrievably escapes to the moderator cover gas. However, the direct activation of helium-3, contained in a closed loop such as the annulus gas system, for example, would be essentially complete within a few weeks without any significant loss.     

SPE固体电解质氚水浓集装置及其应用

简述了SPE固体聚合膜氚水自动电解浓集装置的工作原理，介绍了在研制该装置中所进行的实验与工作进展，用SPE氚水电解浓集装置处理。IAEA第6次低水平氚国际比对样品(TRIC2000)，取得了满意的测量结果。     

Optimization for the tritium isotope separation factor and permeation by selecting temperature and thickness of the diffusion Pd-Ag alloy cathode

Large quantities of tritiated water will be produced in the controlled fusion reactors for power generation. To eliminate the concentrated tritiated water and for recycling tritium, an industrial electrolyzer was developed. The aim of this paper is to give the design of this electrolyzer and the results for optimization in diffusion and in isotopic exchange by selecting thickness of a thimble-shaped Pd-25%Ag cathode working at high temperature and current. In this process, the tritium recovery system is based on the principle of the tritium diffusion Pd-Ag cathode which produces very pure hydrogen isotopes from enriched tritiated water.     

土壤和水中放射性核素实验室间测量比对

介绍了2015年度由本实验室组织的关于土壤和水中放射性核素实验室间测量比对的相关情况。土壤分为掺标土壤和实际土壤两类,水为掺标样品。掺标样品的比对项目包括³H(土壤中不分析)、⁹⁰Sr、⁶⁰Co、¹³⁴Cs和¹³⁷Cs,实际土壤的比对项目包括²³⁸U、²³²Th、²²⁶Ra、⁴⁰K、⁹⁰Sr和¹³⁷Cs。8家单位(11个实验室)参加了本次比对活动,比对结果整体良好。针对比对活动中发现的问题进行了分析,并对以后的比对活动提出了建议。     

Improved modelling of helium and tritium production for spallation targets

Reliable predictions of light charged particle production in spallation reactions are important to correctly assess gas production in spallation targets. In particular, the helium production yield is important for assessing damage in the window separating the accelerator vacuum from a spallation target, and tritium is a major contributor to the target radioactivity. Up to now, the models available in the MCNPX transport code, including the widely used default option Bertini-Dresner and the INCL4.2-ABLA combination of models, were not able to correctly predict light charged particle yields. The work done recently on both the intranuclear cascade model INCL4, in which cluster emission through a coalescence process has been introduced, and on the de-excitation model ABLA allows correcting these deficiencies. This paper shows that the coalescence emission plays an important role in the tritium and ³He production and that the combination of the newly developed versions of the codes, INCL4.5-ABLA07, now lead to good predictions of both helium and tritium cross-sections over a wide incident energy range. Comparisons with other available models are also presented.