锂铅合金中氚扩散行为的理论研究

锂铅合金是非常有前途的聚变堆、聚变-裂变混合堆包层产氚材料,研究氚在其中的扩散行为是很有意义的工作.从氢在金属中扩散的宏观规律出发,依据平板模型初步建立了氚-锂铅体系的扩散模型,利用相关文献数据,探讨了不同研究方式、氚浓度、温度对扩散行为的影响,分析了这种扩散的微观机制.计算结果表明:造成研究结论之间巨大差异的原因在于锂铅表面物理和化学状态的不同考虑;在一定温度范围内,氚浓度的升高引起扩散系数的下降,温度的升高引起扩散系数的增加.     

Li_3TaO_4粉体的制备及表征

钽酸锂作为一种具有潜在应用价值的新型固体氚增殖剂,主要有三种化合物:LiTaO3,Li3TaO4和Li7TaO6,Li3TaO4具有较高的锂密度(0.46g/cm3),还具有高熔点(1400℃)、良好的热学稳定性和较高的热导率等特点。本文采用固相反应法制备出高相纯(99%)、小粒径(1.4μma.v)的β-Li3TaO4粉末。并从锂密度、相结构稳定性、热学稳定性和热导率方面讨论了Li3TaO4作为氚增殖剂备选材料的可能性。     

锂锡合金中氚扩散行为的计算

锂锡合金是非常有前景的聚变能源堆液态包层产氚材料,研究氚在其中的扩散行为是很有意义的工作.本文从氢在金属中扩散的宏观规律出发,依据平板模型初步建立了氚-锂锡体系的扩散模型,利用相关文献数据,探讨了不同研究方式、氚浓度、温度对扩散行为的影响,分析了这种扩散的微观机制.计算结果表明:造成研究结论之间巨大差异的原因在于锂锡表...     

液态锂铅合金中微量氚的回收

解决全球能源问题的聚变反应堆一直备受关注,其中由欧盟、俄罗斯、中、韩、印、日等多方合作的ITER(International Thermonuclear Experimental Reactor)计划便是一个代表性的进展标志.ITER实验包层工作组将液态锂铅实验包层模块列为重点开发对象,中国提出的双功能锂铅实验包层模块DFLL-TBM(Dual FunctionLithium Lead-Test Blanket Module)是主要研究方案之一,液态锂铅集氚增殖剂、冷却剂和中子倍增剂于一身,可采用鼓泡器方式实现氚的提取.有关含氚固体废物的回收早有报道,但主要集中于贮氢材料中氚的同位素交换和氘氚化锂残渣中的氚回收,而高温液态合金中氚的回收还未见报道.如果要将液相锂铅中的氚滞留量降低到包层设计的要求,则必须使其上方的氚分压不超过107Pa,采用单纯的氦吹洗或真空脱气难以满足要求,102Pa是它们所能达到的最低极限压力,这是因为在低氚浓度下,由液相转入气相的氚速率是受氚在液相、气相及气-液界面的扩散过程所限制.为了提高从锂铅合金中回收氚的效率,减小氚在液相和气相的分子扩散阻力及气体在液相的滞留时间,本文采用氦吹洗气以及其与氢、氘的混合气作为交换载带气,利用同位素效应(isotopic effect),对液态锂铅合金中的微量氚开展实验回收的预先研究,期望对今后包层氚提取系统(TES)的工程化设计与建造提供技术支持.研究结果显示:随着交换温度的升高,氚的回收率明显增加,并且温度越高,第一次解吸的氚量越大.623K时,同位素交换效果较差,氚回收率较低;723K时经过6次交换后氚的回收率为78.2%;823K时交换一次氚的回收率就可达到66.3%.在相同温度下,氚回收率随交换次数的增加而增加,但经过6次交换后,曲线趋于平坦,氚回收率似乎在接近80%左右形成最大值.此外,单独使用氦吹洗气,氚回收率不到30%;添加0.1%的氘比氢的回收率要略高一些,这是因为充氚结束后的锂铅合金处于平衡状态,并非饱和状态,要交换出合金内的氚,必须预先吸附一定量的载带气,使其达到交换温度下的气体平衡离解压力,方可将合金中的氚交换出来.在较高的交换温度下,氚比氘、氘比氢更容易从锂铅中解析出来,这与气相色谱法分离氢同位素的原理是一致的.但过度增加载带气中氘的比例,反而降低了氚回收率,这是因为随着氘分压的增大,吸附质之间的同位素效应将减弱.总之,采用氦与0.1%氘组成的混合吹洗气,利用同位素交换效应对锂铅合金中的微量氚进行回收是有效的,氚回收效率接近80%;交换温度和交换次数对氚回收率的影响显著,在载带气相同的情况下,温度越高,交换次数越多,氚回收率越高.     

氚化学与工艺

氚作为一种重要的资源,在国防科技和国民经济领域有着广泛的应用。伴随着国防科技发展需求的不断提高,中国工程物理研究院在氚化学与工艺研究方面取得了一定的成就,研究领域涉及到氚的整个生命周期,包括生产、分离、储存、应用及氚废物治理等。本文重点介绍了中国工程物理研究院近年来在金属氚化物、储氚材料、氢同位素分离技术、含氚重水提氚...     

锆-氚反应热力学特性

<正>利用金属氢化物可以方便地对氢同位素氕、氘、氚进行泵输、转移、固态吸附贮存、功能薄膜制造等。目前应用较成熟的有铀[1]、钛[2]、锆钴合金[3]等材料。锆与钛是属于同一族的金属元素,也是一种吸氢密度很高的功能材料,目前国内外已有较多关于氢在锆中固溶[4]、扩散[5-6]等方面的报道,但有关锆吸氚性能     

氚核磁共振波谱在氚标记甾族化合物制备中的应用

本文介绍了十一种氚化甾族化合物的氚核磁共振谱。我们依照英国放化中心和英国萨里大学报道数据,(甾体骨架上的CH及CH_2各位置的谱线归属,应用了定位标记化合物作为对照)归属了其氚在化合物中标记的位置,根据其积分曲线定出了各位氚的相对百分含量。同时图谱中又提供了立体构型的信息,为氚化甾族化合物制备过程中,催化剂的选择,实验条件的控制及反应机理等研究提供了理论依据。     

某些氚标记杂环化合物的~3H NMR研究

本文介绍了应用液-液催化、氢-氚交换法制备某些氚标记杂环化合物。采用PtO_2作为催化剂,选用含有杂氮原子的、杂氮和杂硫原子的、杂氧原子的十二种化合物作为研究对象,并用~3H NMR研究了氚在这些杂环化合物中的位置以及它在分于中的相对丰度,得到了满意的氚渗入结果。     

锑酸消除空气中的氚

采用锑酸作为消气材料,锑酸与钯黑共同压制成消氚电极,考察在82.2L的系统中电压、消氚圆片大小、氚初始浓度、空气湿度等因素对消除空气中氚的速度的影响以及消氚的实际应用效果。结果表明:空气气氛中,在达到107Bq/L量级的氚量下,当消氚片面积达到0.025m2左右,消氚效率可达80%~90%,加电压不影响消氚效率。同样的消氚片,在N2气氛中消氚试验结果与在空气气氛中相似,均能达到90%左右,表明氚是以质子或自由基形态通过钯黑传导至锑酸,再被锑酸吸收。     

国防领域放射分析化学

放射分析化学在国防领域中一直发挥着十分重要的作用,研究方向主要包括气体和固体样品放射化学分离技术,α、β、γ能谱及同位素质谱放射性测量技术,与氚工艺相关的产氚陶瓷制备及性能、氢同位素化学、聚变燃料循环等。本文简要介绍了中国工程物理研究院在上述方向的部分基础性研究工作,并展望了放射分析化学研究的前景。     

铀床氚残留量的测量

分别采用直接测量法、同位素交换法和溶解法测量铀床中的氚残留量, 并分析了这三种测量方法在本实验条件下的误差. 直接测量法测量铀床的氚残留量的结果如下: 铀床的氚残留量为2.68%, 即每克铀含(0.0308±0.0003) mmol 氚气; 当压力读数在1500～133332 Pa之间时, 基于理想气体状态方程的测量方法(简称PVT法)的标准差小于0.95%. 同位素交换法测量铀床氚的结果如下: 加热充分解吸过的铀床经多次同位素交换后, 其交换效率仅为2.84%, 即不到3%(摩尔分数)的氚被氘气载带出来, 其同位素交换法测量的标准差为7.35%. 溶解法能够彻底地测量铀床中残留的氚, 其溶解法测量的标准差为6.49%.     

Novel Non-Evaporable Getter Materials and Their Possible Use in Fusion Application for Tritium Recovery

Non-evaporable getters (NEGs) are metallic compounds of the IV group, particularly titanium and/or zirconium-based alloys and are usually used as pumps in vacuum technologies since they are able to sorb, by chemical reactions, most of the active gas molecules, with particular efficacy towards hydrogen isotopes. This work suggests an alternative application of these materials to fusion nuclear reactors, where there is the need to recover small amount of tritium from the large helium flow rate composing the primary coolant loop. Starting from the tritium mass balance inside the primary coolant loop, the amount of coolant to be routed inside the coolant purification system (CPS) is identified. Then a feasibility study, based on the bulk getter theory, is presented by considering three different commercial alloys, named ST707, ST101 and ZAO. The results provide the mass, the area and the regeneration parameters of the three different alloys necessary to fulfill the requirements of the CPS unit. By comparing the features of the three alloys, the ZAO material appears the most promising for the proposed application because it requires the lower amount of material and a lower number of regeneration cycles.     

A Procedure for Determination of Tritium in Potassium

Abstract

A procedure has been developed for the quantitative analysis of potassium for its tritium content. This procedure consists of dissolving the highly reactive alkali metal in an inert liquid containing a small amount of ethanol and then analyzing the resulting solution for its tritium content by classical methods. Techniques previously used for sodium analysis are reviewed and discussed as they apply to the more reactive potassium.     

Synthesis of Tritium and Deuterium Labelled Agmatine

Agmatine is a promising anti-opioid dependence and relapse drug1~2 discovered and developed by Beijing Institute of Pharmacology and Toxicology, but the physiological role of agmatine in inhibition of tolerance to and dependence on opioid are not well est…     

Tritium measurements by AMS and applications

The Accelerator mass spectrometry (AMS) analysing method is described with applications for the detection of tritium leaks, detection of pollution and for research in the fusion experiments. The special requirements for an experiment of AMS with tritium are also presented. This paper concludes by showing the possibilities for each AMS facility to perform applications for detecting and preventing the environment pollution with tritium.     

紫外线激活氚原子—制备氚标记单磷酸阿糖腺苷的研究

本文采用紫外线激活氚原子的方法,进行氚-氢同位素交换反应,制得氚标记单磷酸阿糖腺苷(9—~3H—mparaA)。产品的纯度是层析纯;放射性比活度16GBq.m mol~(-1);放射化学纯度92.0%。本法的优点是:交换反应温和、反应时间较短、不易破坏生物活性、引起的副产物少、产品分离和纯化较方便。     

Moderator effects on recoil tritium reactions with lithium beta-phenylpropionate

The recoil tritium reactions were studied with lithium beta-phenylpropionate having both the aromatic and aliphatic C-H bonds in the molecule, mainly in terms of the moderator effect on the intramolecular tritium distribution. Recoil tritium atoms were produced by the 6Li(n,alpha)3H reaction. Water molecules were used as the moderator. The tritium activity of the ethylene group represented relative to that of the corresponding ring assumed as a standard (= 100) is 30 in the moderator-free system and is reduced to 13 in the moderated system in which the H2O/beta-PhC2H4CO2Li mole ratio is 328. In the ring, the tritium distribution shows a slight ortho- and para-orientation in the moderator-free system and the selectivity is pronounced when the H2O/beta-PhC2H4CO2Li mole ratio is large. The data show that the aromatic ring tritiation in the moderated system is given by increasing contribution of the reactions of tritium atoms having lower energy than the threshold energy of the ethylene group tritiation.     

A fundamental study on testing candidate tritium breeders for fusion reactiors

An apparatus was designed and constructed for investigation of the tritium release rate from neutron-irradiated materials for fusion reactors. The design principles, as well as safe handling of tritium and complete trapping of tritium components released, are described and the tritium release rates obtained with this apparatus are discussed for sintered lithium fluoride pellets.