复合防氚材料阻氚性能的测定

本文介绍借助以水捕集渗透氚的方法测定复合防氚材料阻氚性能的原理、实验装置和结果。实验结果表明,不同的复合防氚材料相对于74~#氯丁像胶的氚气渗透率约为1/(29)—1/(16),说明这些材料的阻氚性能普遍优于氯丁橡胶。     

氚在真空贮存容器材料中的吸附和渗透行为

研究了贮存氚靶约4 a和20 a的两个316 L不锈钢真空贮存容器(以下简称贮存容器)及其垫片材料对氚的吸附行为,并对氚在贮存容器材料中的渗透速率进行了测量和分析。结果表明,贮存容器外表面氚污染为几十Bq/cm2,不锈钢与陶瓷中吸附的氚活度均为106Bq/g;热解吸至1 273 K过程中,材料中99%的氚释放出来;在解吸出的氚中,陶瓷中的HTO比例高于不锈钢;贮存温度对氚靶贮存容器的渗氚速率有较大影响,夏季约为冬季的4倍。上述结果提示,氚在贮存容器材料内表面吸附后,一部分会向晶格扩散并滞留下来;另一部分则透过材料向外环境渗透,其中温度是影响氚向外环境渗透的主要因素之一。     

用氢同位素估算氚在熔盐堆结构材料中的渗透

熔盐堆产生的氚在高温下透过结构材料管壁进入大气环境。为降低此危害,研究氚在堆结构材料中的渗透过程十分必要。针对熔盐堆常用的结构材料Hastelloy N、GH3535、Hastelloy C230、Hastelloy C276,本研究采用压力差驱动法,在400-700 oC和5-40 k Pa的试验条件下,获得了氕、氘的渗透系数,并初步估算氚在该结构材料中的渗透。结果表明:氕、氘在镍基合金中的渗透通量与气体压力的平方根成正比,渗透系数随温度增大,与温度倒数的关系符合阿伦尼乌斯公式;氕、氘在成分相似的GH3535和Hastelloy N中渗透系数接近,与其它两种合金材料中渗透系数都在一个数量级内,在相同温度下两者渗透系数比值接近1.4,符合经典扩散理论;在400-700 oC内,氚在4种镍金合金中渗透过程的指前因子为1.1×10-7-1.6×10-7 mol·m-1·s-1·Pa-1/2,活化能为59-62 k J·mol-1。     

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。     

ITER中国液态锂铅实验包层模块氚渗透分析

对ITER中国液态锂铅实验包层模块的氚渗透途径进行了初步分析,并建立了氚渗透模型;在确保环境安全的前提下,通过计算LiPb中的氚分压分析了氚渗透量及氚总量的分配情况;在此基础上通过改变进入氚提取系统中LiPb比例(F)和涂层氚渗透减少因子(TPRF)对氚提取及渗透的影响做了灵敏性分析.     

氚气在弹性复合材料中的溶解、扩散和渗透性能的测量

本文根据氚气具有很强渗透性能及其在不同材料中渗透性能的差异,用正比计数测量技术对氚气在各种材料中的渗透性能进行测量、比较,从中选出最佳复合形式,提供生产制造防氚手套。     

氚气(T_2、TH)内照射剂量监测的特殊性

通过对氚气接触者尿中氚水和有机氚的排泄规律的实验研究,评论了现行氚气内照射剂量监测方法的缺点。指出,如不考虑有机氚所致的约定剂量当量,则可造成偏低16%;而把有机氚所致的也当作氚水之贡献,则会偏高4倍。给出了有效的有机氚测量程序。对氚气内照射剂量监测方案提出了改进意见。     

Al_2O_3(SiO_x)/PVC复合材料的研制和防氚性能测试

本文介绍了三种无机/有机防氚复合材料,即SiOx/PVC复合材料、Al2O3/PVC复合材料、Al2O3/SiOx/PVC复合材料的制备,并与普通PVC材料进行了防氚效果测试比较。结果显示,在1atm,氚气浓度为7.48×108Bq/L的情况下,三种复合材料对氚的渗透率分别为2.88×104Bq/(cm2·h)、2.09×104Bq/(cm2·h)、0.64×104Bq(/cm2·h),较普通PVC材料氚渗透率7.18×104Bq(/cm2·h)明显降低;三种复合材料氚渗透达到稳态的延迟时间分别为18.8、20.1、63.7h,明显大于普通PVC的2.1h。说明相对于普通PVC材料,三种复合材料对氚的渗透率低、延迟时间长、有较好的阻氚性能。其中Al2O3/SiOx/PVC复合材料的性能最好,明显优于氯丁橡胶。     

重水堆核电厂在线测氚系统抽气方式的改进

重水堆核电厂利用电离室分析技术进行氚浓度监测。为解决其在线实时氚测量系统不能连续对多个区域进行测量的不足,提高测氚系统可靠性,对测氚系统抽气方式进行了改进。在线按序测氚改进后的测量结果,提高了氚浓度测量的准确性和实时性,为核电厂反应堆厂房内的氚泄漏定位和人员辐射防护提供了重要依据。      

植物样品中有机氚测量方法的初步研究

为研究植物样品中有机氚（OBT）浓度相关测量的最佳方法,以秦山核电基地所采植物和人为氚污染的植物样品为研究对象,对去除交换性有机氚(E-OBT)所需的最合适浸泡水用量和浸泡时间及样品氧化燃烧和收集过程中氚的残留效应进行了研究。结果表明：用30倍于干物质质量的低氚水浸泡24 h,可有效去除植物样品中的E-OBT;用50 mL低氚水冲洗氧化燃烧炉1次,即可将残留在其中的氚冲洗干净;经3次大量低氚水冲洗后OBT水样收集瓶与石英舟中无氚残留。     

厚度和湿度对氚在一些橡胶和塑料中的渗透率的影响

为了研究材料结构的完整性及其湿度对氚的渗透率的影响,我们在过去工作的基础上,进行了材料厚度和湿度对氚在一些橡胶和塑料中的渗透率的实验测量工作。     

Development of a plasma driven permeation experiment for TPE

Experiments on retention of hydrogen isotopes (including tritium) at temperatures less than 800 °C have been carried out in the Tritium Plasma Experiment (TPE) at Idaho National Laboratory [1], [2]. To provide a direct measurement of plasma driven permeation in plasma facing materials at temperatures reaching 1000 °C, a new TPE membrane holder has been built to hold test specimens (≤1 mm in thickness) at high temperature while measuring tritium permeating through the membrane from the plasma facing side. This measurement is accomplished by employing a carrier gas that transports the permeating tritium from the backside of the membrane to ion chambers giving a direct measurement of the plasma driven tritium permeation rate. Isolation of the membrane cooling and sweep gases from TPE's vacuum chamber has been demonstrated by sealing tests performed up to 1000 °C of a membrane holder design that provides easy change out of membrane specimens between tests. Simulations of the helium carrier gas which transports tritium to the ion chamber indicate a very small pressure drop (∼700 Pa) with good flow uniformity (at 1000 sccm). Thermal transport simulations indicate that temperatures up to 1000 °C are expected at the highest TPE fluxes.     

Tritium management and anti-permeation strategies for three different breeding blanket options foreseen for the European Power Plant Physics and Technology Demonstration reactor study

In DT fusion reactors like DEMO, the commonly accepted tritium (T) losses through the steam generator (SG) shall not exceed about 2 mg/d that are more than 5 orders of magnitude lower than the T production rate of about 360 g/d in the breeding blanket (BB). A very effective mitigation strategy is required balancing the size and efficiency of the processes in the breeding and cooling loops, and the availability and efficiency of anti-permeation barriers. A numerical study is presented using the T permeation code FUS-TPC that computes all T flows and inventories considering the design and operation of the BB, the SG, and the T systems. Many scenarios are numerically analyzed for three breeding blankets concepts – helium cooled pebbles bed (HCPB), helium cooled lithium lead (HCLL), and water cooled lithium lead (WCLL) – varying the T processes throughput and efficiency, and the permeation regimes through the BB and SG to be either surface-limited or diffusion-limited with possible permeation reduction factor. For each BB concept, we discuss workable operation scenarios and suggest specific anti-permeation strategies.     

秦山核电厂二期扩建工程反应堆保护系统设计中核安全原则的应用

秦山核电厂二期扩建工程(3~#、4~#机组)反应堆保护系统的设计是在秦山核电厂二期工程(1~#、2~#机组)反应堆保护系统设计的基础上经过改进而成的.本文通过对一个经过论证且已实施的改进项和一个由业主提出但没有被采纳的改进项的分析,阐明了保护系统设计中核安全原则的应用:让反应堆更加安全,使电站在发生事故后能够将反应堆转入并保持在安全状态.如果对反应堆保护系统设计的修改能够在不影响核电站安全性的同时提高电站的经济性,那就是可行的.否则,无论其能带来多么可观的经济利益,都不宜采用.     

启明星1号装置中子通量能谱与中子平均能量计算

启明星1号装置是我国研究ADS次临界中子学的一个快热耦合系统。本文用离散坐标法的程序TWODANT对启明星1号装置能谱进行分析计算。计算结果表明，启明星1号装置具有比较硬的中子能谱，可用以进行有关ADS的研究。     

Design and development of hydrogen isotope sensor in liquid PbLi

Indian LLCB – TBM uses liquid Lead-Lithium (Pb-Li) as tritium breeder, neutron multiplier and coolant. Tritium bred in liquid PbLi stream has to be recovered by tritium extraction system. Therefore, a reliable sensor with quick response time for measurement of hydrogen isotope is essential.A hydrogen isotope sensor in liquid Pb-Li, based on permeation of hydrogen isotopes through metal (sensor material) is designed. The capsule shaped sensor, made of iron membrane coated with Pd from inside (downstream side), allow hydrogen isotope to permeate through it. The design work mainly includes the selection of proper material, its thickness and surface conditions, which is to be supported by numerical calculations for optimization of maximum permeation flux, fast response and fabricability. The numerical calculation utilizes a physical model having recombination of two hydrogen isotope atoms at the surface and atomic diffusion through the bulk. In this work, design calculations based on numerical simulation and fabrication procedure of the hydrogen isotope sensor are presented.     

Tritium permeation in EUROFER in EXOTIC and LIBRETTO irradiation experiments

The reduced activation martensitic steel (RAFM) EUROFER is foreseen as a structural material in test breeder module (TBM) in ITER and breeder blanket in DEMO design. In a number of irradiation experiments conducted in high flux reactor (HFR) in Petten EUROFER was used as a containment wall of the breeder material, through which tritium permeation was monitored on line. Thus in EXOTIC-9/1 (EXtraction Of Tritium In Ceramics) experiment where Li₂TiO₃ pebbles were the breeder material, EUROFER was irradiated up to 1.3 dpa at 340–580 °C. In LIBRETTO experiments (LIBRETTO-4/1, -4/2 and -5) the breeder material was lead lithium eutectic which was in direct contact with the EUROFER containment wall. The neutron damage in steel achieved in the LIBRETTO experiments varied from 2 to 3.5 dpa. The irradiation temperature was 350 °C (LIBRETTO-4/1), 550 °C (LIBRETTO-4/2), and 300–500 °C (LIBRETTO-5).Tritium permeability was studied by varying the irradiation temperature and hydrogen concentration in the purge gas. From the analysis of the temperature transients performed in all four experiments yielded the tritium diffusion coefficients were derived, which appear to be factor ten lower than the literature data obtained in the gas driven permeation experiments.     

氚水在大鼠和小鼠体内的分布、代谢、转移及剂量估算

本文汇总报道了氚水在大鼠和小鼠体内的分布、代谢、转移及剂量估算研究结果:(1)氚在小鼠体液及各组织中按指数下降规律呈均匀分布;(2)非妊娠鼠总氚的第一生物半排期约2 d,孕鼠和泌乳鼠分别约1.6和1.7 d,氚在母鼠、孕鼠和泌乳鼠体内的代谢规律基本一致;(3)大鼠组织中的氚活度分布不均匀,第15天组织中的滞留活度约占第1天的9％左右。(4) 氚化小麦组大鼠组织内总氚和有机结合氚均明显高于氚水组;(5)氚水可通过受伤皮肤吸收进入体内,不同受伤程度的皮肤对氚的吸收率为切割伤>磨擦伤>烫伤>化学烧伤;(6)小鼠妊娠期和泌乳期母体内氚可通过不同途径转移给胎儿和仔鼠,转移系数在1.06～2.37之间;(7)小鼠母鼠、妊娠鼠和泌乳鼠总氚累积吸收剂量分别为8.5、6.7和7.1 mGy。     

氚在一些弹性材料和聚合材料中渗透率的测量

在制造氚容器、氚操作系统(如手套箱)的材料中,弹性材料和聚合材料是十分重要,而且几乎是不可缺少的材料。例如,各种橡胶、塑料和密封用的粘接材料都广泛应用于制造手套、垫圈、维修用帐篷以及氚防护服等。氚在这些材料中的渗透率一般都比在金属中