联合电解催化交换系统HD／H2O和HT／H2O体系模拟

计入蒸汽的影响，研究建立基于两步传质的联合电解催化交换系统模型，计算HD／H2O和HT／H2O两个体系的分离性能。传质系数的提高能显著改善交换系统的整体性能，电解池浓缩倍数与电解池滞液量有关。电解池中氘浓度的增长最终将引起交换系统脱氘率的下降，这一现象表明，在交换系统操作模式选择以及与后级浓缩系统的级联匹配中，对交换系统的动态行为必须予以特别关注，并应在交换床设计中考虑此因素。     

联合电解催化交换系统HD/H2O和HT/H2O体系模拟

计入蒸汽的影响，研究建立基于两步传质的联合电解催化交换系统模型，计算HD/H₂O和HT/H₂O两个体系的分离性能。传质系数的提高能显著改善交换系统的整体性能，电解池浓缩倍数与电解池滞液量有关。电解池中氘浓度的增长最终将引起交换系统脱氘率的下降，这一现象表明，在交换系统操作模式选择以及与后级浓缩系统的级联匹配中，对交换系统的动态行为必须予以特别关注，并应在交换床设计中考虑此因素。     

聚变反应堆含氚废水处理系统的设计

以联合电解催化交换-气相色谱(CECE-GC)为技术路线基础,对聚变反应堆(International thermonuclearexperimental reactor,ITER)含氚废水处理系统(Water detritiation system,WDS)进行了总体设计和主要子系统的设计.与目前的重水提氚演示系统相比,ITER-WDS的不同之处在于不使用氢氧复合器,不采用碱性电解池而使用固体聚合物电解池(Solid polymer electrode,SPE),增加了Pd/Ag膜渗透系统进行氚的回收.     

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)%。     

氚在不锈钢中的体扩散行为

采用酸液蚀刻法和液体闪烁法数法测量了在６７３Ｋ和１０１３Ｋ下分别充氚８ｈ、室温空气中时效１～３ａ后，３１６Ｌ型和２２－１３－５型不锈钢圆柱样品氚浓度的分布。运用扩散方程的有限差分数值解法，计算了样品中氚和氦－３的体浓度分布，结果与实验结果符合较好。研究结果表明，室温时效期间，氚在不锈钢中的扩散缓慢，主要通过衰变成氦－３后发生浓度变化；由于氧化层的影响，表面附近的氚只是部分逸出；样品中存在“固溶”和     

液闪法直接测定尿中氚

介绍了用液闪法直接对氚操作人员的尿氚监测。制作了尿氚猝灭校正曲线，修正了尿中氚浓度的直接测量结果。方法具有足够的灵敏度，能简便地、快速地测量大量氚操作人员的尿氚浓度。     

D2/DT低温精馏分离动态模拟

本文建立了氢同位素低温精馏分离的动态模型,利用该模型针对D2/DT体系计算获得了精馏柱上DT浓度的动态变化和空间分布;研究了再沸器滞留量、回流比等参数对系统分离性能的影响.回流比的提高可以显著地提高脱氚率;再沸器中DT浓度不但与滞液量存在显著的依赖关系,而且随时间增长而增长.在理论板数为80时,塔顶与塔底DT浓度相差约3个数量级,分离效果明显.     

充氚不锈钢中氦泡长大行为的加热效应

以室温贮存经历的充氚不锈钢试样为研究对象,计算了充氚不锈钢中氚、氦浓度的深度分布,利用透射电镜观察了充氚不锈钢在加热过程中氦泡的演化行为。结果表明:在氚压0.131MPa、780℃充氚8h后,不锈钢中氚在深度方向分布均匀,平均浓度为110μL/L;在空气室温环境下放置6a后,不锈钢中氚衰变的氦浓度在深度方向分布均匀,平均浓度为60μL/L;对充氚不锈钢加热处理后,在550℃/1h时效即可观察到氦泡;在950℃/1h和1050℃/1h时效时,氦泡明显长大,大的可达100nm,小的可达30nm,在晶界、晶内和位错处均可见氦泡。     

金属样品残余氚测量方法

为定量评价氚在结构材料和老龄贮氢材料内部的滞留量,用化学蚀刻法测定不锈钢内部氚浓度大小、分布情况及同位素交换后老龄贮氚铀床的氚滞留量。结果表明,贮氚13年的不锈钢样品中氚主要存在于样品内表面由表及里的120μm范围内,样品蚀刻深度110.6μm范围内,不锈钢的平均氚滞留量～9.37×10-4mmol/g,贮氚铀粉平均氚滞留量～4.16×10-5mmol/g。该方法对测量金属中微量氚有较高灵敏度,可检测金属中残余氚的滞留量。     

三种疏水催化剂耐氚辐照稳定性初步研究

为考察3种疏水催化剂Pt-SDB(SDB为苯乙烯-二乙烯苯共聚物)，Pt-PTFE（PTFE为聚四氟乙烯），Pt-C-PTFE 的耐氚辐照稳定性，将其置于1.26×10¹²Bq/L的氚水中静态辐照210 d后，对其催化交换性能及催化剂中残存氚进行分析。结果表明，3种催化剂在氚的β辐照下未发生裂解，催化剂中氚的残存量随催化剂比表面积的增加而增加，基本没有发生结构上的氚取代反应；但在氚水辐照后，3种疏水催化剂的交换性能出现了不同程度的变化，按单位质量Pt粒子计算，在测试不确定度范围内Pt-PTFE和Pt-C-PTFE的转化率没有发生明显变化，Pt-SDB(1)的转化率下降了11.2％，Pt-SDB(2)的转化率下降了16.9％。     

101重水研究堆含氚轻水脱氚方案研究

101重水研究堆(HWRR)是中国第一座核反应堆,现已停堆进入退役准备期。其乏燃料水池和废水贮存罐中存有一定量的含氚轻水,含氚浓度较高,需进行脱氚处理。本文针对HWRR含氚轻水的处理量和含氚浓度,分别评价了3种含氚水脱氚方案:两种联合电解催化交换(CECE1和CECE2)工艺和水蒸馏(WD)工艺。结果表明,与WD相比,CECE工艺的塔径和塔高更小,CECE电解槽的能耗也较WD工艺的蒸发器稍低;两种CECE工艺相比,顶部进天然水的CECE2工艺更适合处理HWRR的含氚轻水。     

Preliminary results from a detritiation facility dedicated to soft housekeeping waste and tritium valorization

Nuclear waste management has to be taken into account for fusion machine using tritium as fuel. Soft housekeeping waste (e.g. gloves, tissues, protective clothes, etc.) is produced during the whole life as well as during the dismantling of the reactor and is contaminated by tritium under reduced (HT) and oxidized (HTO) forms.In collaboration with ENEA, a lab-scaled facility has been built at CEA Cadarache for soft housekeeping waste detritiation and tritium valorization. The previously milled waste is placed in a reactor to be heated up to a temperature lower than the housekeeping melting point. A carrier gas is then injected in the detritiation reactor to remove tritium, thanks to the combined effects of temperature and carrier gas (type and feed flow). The tritiated gas exhausted from the detritiation reactor is then sent through a catalytic Pd–Ag membrane reactor (CMR) where tritium is recovered via isotopic exchange reaction and permeation phenomenon.Based on previous studies that have allowed defining the most efficient operating conditions for the detritiation process, this work presents the results obtained by the coupling of the detritiation facility with the CMR. Due to safety considerations, restrictions on the nature of the carrier gas were applied, rejecting air as the carrier gas even though air was the best candidate for the detritiation part of the process. The performance of the whole system was estimated by means of a parametric study on the influence of flow rates in the CMR and transmembrane pressure.     

带自动控制功能的除氚系统

针对氚工艺尾气处理的需求和源项实际情况,根据化工原理和氚特性设计含自动控制功能除氚系统的主要部件、自动控制功能和初步性能测试,得出催化反应器、氚水吸附床等部件的结构尺寸,催化剂、干燥吸附剂的装填量等参数及控制软件界面;通过除氘和除氚实验初步测试了除氚系统的处理性能。结果表明,在循环处理模式下,1m3密闭容器中氘体积比6.0×10–4–2.8×10–2范围内时,35min内氘气浓度降低两个量级;5次对30L密闭容器内不同浓度的含氚气体处理,60min内对氚的去除效率均达到95%以上。     

Design Study of Feasible Water Detritiation Systems for Fusion Reactor of ITER Scale

Two types of water detritiation systems have been designed for fusion reactors of ITER scale. One of the systems is a combination of WD (Water Distillation) and VPCE(vapor phase catalytic exchange) columns. The other is a combination of a WD column and a CECE(combined electrolysis catalytic exchange) column. Three water distillation columns are needed for the former system. The total height of the three columns is 106 m. The height of the water distillation and CECE columns for the latter system are 20 and 24m, respectively. These large water distillation columns result in the larger tritium inventory of the former system than for the latter system. However, there have been the results for the operation of the actual scale of the water distillation and VPCE columns. No demonstration test has been carried out for the CECE column. From these reasons, the WD+VPCE system should be the first candidate for the fusion reactor. The WD+CECE system is superior to the WD+VPCE system for the flexibility in design as well as the tritium inventory. It is desired to demonstrate the CECE column to develop the water detritiation system best suited to the fusion reactors.     

Influence on moisture and hydrocarbons on conversion rate of tritium in catalytic reactors of fusion-DEMO detritiation system

Thoughtful consideration of abnormal events such as fire is required to design and qualify a detritiation system (DS) of a nuclear fusion facility. Since conversion of tritium to tritiated vapor over catalyst is the key process of the DS, it is indispensable to evaluate the effect of excess moisture and hydrocarbons produced by combustion of cables on tritium conversion rate considering fire events. We conducted demonstration tests on tritium conversion under the following representative conditions: (I) leakage of tritium, (II) leakage of tritium plus moisture, and (III) leakage of tritium plus hydrocarbons. Detritiation behavior in the simulated room was assessed, and the amount of catalyst to fulfill the requirement on tritium conversion rate was evaluated. The dominant parameters for detritiation are the concentration of hydrogen in air and catalyst temperature. The tritium in the simulated room was decreased for condition (I) following ventilation theory. An initial reduction in conversion rate was measured for condition (II). To recover the reduction smoothly, it is suggested to optimize the power of preheater. An increase in catalyst temperature by heat of reaction of hydrocarbon combustion was evaluated for condition (III). The heat balance of catalytic reactor is a point to be carefully investigated to avoid runaway of catalyst temperature.     

空气除氚系统中氚氧化催化剂的研究进展

在大型氚设施中空气除氚系统必不可少,通过气-水转换除去气态氚是目前应用最广泛也是最有效的工艺,过程中氧化催化剂至关重要。总结了气态氚的催化氧化研究进展、催化剂的催化性能及影响催化性能的主要因素。贵金属Pt和Pd在室温下对氚的转化效率接近100%,因而被广泛用于氚的催化氧化。通过负载分散载体、添加催化助剂、使用规整结构催化剂、设计新型的催化反应器能够进一步提高催化剂性能。以蜂窝状催化剂为研究热点的规整结构催化剂以其高比表面积和低压力降而显示出良好的催化性能,将它用于氚的催化氧化,是该领域的一个研究方向。氢、氘、氚在氧化过程中的同位素效应会影响除氚效率,需进行深入研究。     

TBM TES手套箱泄漏事故下氚浓度与通风关系研究

为了分析TBM TES室内通风是否能在手套箱发生氚泄漏时控制室内氚浓度在安全剂量值,采用Fluent对手套箱的氚泄漏和扩散进行模拟,得到不同通风下手套箱泄漏时的氚泄漏速率以及室内氚浓度分布,并对比分析了模拟数据与理论数据。结果表明TES手套箱泄漏速率为1.41×10~(-5)g/s和1.02×10~(-5)g/s时,分别为5次/h和8次/h的换气通风能控制室内氚浓度在安全剂量值2.0×10~(10)Bq/m~3内;而氚泄漏速率为1.56×10~(-5)g/s时,3次/h的换气通风不能控制室内氚浓度在安全剂量值内;模拟结果与理论结果相一致。结果为TES通风除氚设计提供了理论依据。     

Effect of hydrocarbons on the efficiency of catalytic reactor of detritiation system in an event of fire

Detritiation system of a nuclear fusion plant is mandatory to be designed and qualified taking carefully into consideration all the possible extraordinary situations in addition to that in a normal condition. We focused on the change in the efficiency of tritium oxidation of a catalytic reactor in an event of fire where the air accompanied with hydrocarbons, water vapor, and tritium is fed into a catalytic reactor at the same time. Our test results on the effect of these gases on the efficiency of tritium oxidation of the catalytic reactor indicated; (1) tritiated hydrocarbon produces significantly by reaction between tritium and hydrocarbons in a catalytic reactor; (2) there is little possibility of degradation in the detritiation performance because the tritiated hydrocarbons produced in the catalyst reactor are combusted; (3) there is no possibility of uncontrollable rise in the temperature of the catalytic reactor by heat of reactions; and (4) saturated water vapor could temporarily poison the catalyst and degrades the detritiation performance. Our investigation indicated a saturated water vapor condition without hydrocarbons would be the dominant scenario to determine the amount of catalyst for the design of catalytic reactor of the detritiation system.     

Tritium management and safety issues in ITER and DEMO breeding blankets

Safe, reliable and efficient tritium management in the breeder blanket faces unique technological challenges. Beside the tritium recovery efficiency in the tritium extraction and coolant purification systems, the tritium tracking accuracy between the inner and outer fuel cycle shall also be demonstrated. Furthermore, it is self-evident that safe handling and confinement of tritium need to be stringently assured to evolve fusion as a reliable technique. The present paper gives an overview of tritium management in breeder blankets. After a short introduction into the tritium fuel cycle and blanket basics, open tritium issues are discussed, thereby focusing on tritium extraction from blanket, coolant detritiation and tritium analytics and accountancy, necessary for accurate and reliable processing as well as for book-keeping.     

Overview of the tritium system of Ignitor

Among the recent design activities of the Ignitor program, the analysis of the tritium system has been carried out with the aim to describe the main equipments and the operations needed for supplying the deuterium–tritium mixtures and recovering the plasma exhaust.

In fact, the tritium system of Ignitor provides for injecting deuterium–tritium mixtures into the vacuum chamber in order to sustain the fusion reaction: furthermore, it generally manages and controls the tritium and the tritiated materials of the machine fuel cycle. Main functions consist of tritium storage and delivery, tritium injection, tritium recovery from plasma exhaust, treatment of the tritiated wastes, detritiation of the contaminated atmospheres, tritium analysis and accountability.

In this work an analysis of the designed tritium system of Ignitor is summarized.