中子发生器用氚靶的研究进展

对粒子加速器和密封中子管用氚靶的工作原理、制备过程及基本要求,包括具有较高的载氚密度、较高的热稳定性、氚靶靶膜应具有较低的3He释放率和掉粉率等作了简要介绍.在此基础上,综述了近年来在金属氚化物膜块结构和性质、靶膜表面性质、金属氚化物的氦释放和新型靶材料的研制等方面的进展,提出了今后中子发生器氚靶的研究方向,主要涉及新型靶材料设计开发、新型结构靶研制、氚化物靶膜结构及其氦释放行为研究等方面.     

中子发生器用氚靶的研究进展

对粒子加速器和密封中子管用氚靶的工作原理、制备过程及基本要求，包括具有较高的载氚密度、较高的热稳定性、氚靶靶膜应具有较低的^3He释放率和掉粉率等作了简要介绍。在此基础上，综述了近年来在金属氚化物膜块结构和性质、靶膜表面性质、金属氚化物的氦释放和新型靶材料的研制等方面的进展，提出了今后中子发生器氚靶的研究方向，主要涉及新型靶材料设计开发、新型结构靶研制、氚化物靶膜结构及其氦释放行为研究等方面。     

脉冲离子束作用下金属氚化物氦释放测量技术研究

为认识脉冲离子束作用下金属氚化物的氦释放行为,建立了脉冲离子束作用下金属氚化物氦释放测量系统。利用标准体积气体取样装置,采用气体反扩散法,对系统的容积比、灵敏度进行了实验标定。在此基础上,发展了脉冲离子束作用下金属氚化物氦释放的测量技术,开展了脉冲离子束作用下金属氚化物氦释放实验研究。结果显示,单次脉冲离子束作用下金属氚化物的氦释放呈脉冲式,释放量最大可达10~(13)个原子以上。     

体心立方钨和铁中氦泡生长机制模拟研究进展

体心立方金属钨和铁作为核聚变反应堆的第一壁面向等离子体材料和第一壁结构材料处于高剂量的中子辐照环境中。辐照过程产生的氦原子易在金属内聚集形成氦泡,对材料微观结构和宏观力学性能产生极大影响。本文通过综合分析文献中关于通过第一性原理、分子动力学和蒙特卡罗方法对氦泡形核和生长机制,比较了不同模拟条件下氦泡的演化机制。分析表明,晶界、位错、空位等内部缺陷和温度等外部条件都对氦泡的形核及其生长机制有影响。在此基础上提出了下一步研究方向和思路。     

体心立方钨和铁中氦泡生长机制模拟研究进展

体心立方金属钨和铁作为核聚变反应堆的第一壁面向等离子体材料和第一壁结构材料处于高剂量的中子辐照环境中。辐照过程产生的氦原子易在金属内聚集形成氦泡,对材料微观结构和宏观力学性能产生极大影响。本文通过综合分析文献中关于通过第一性原理、分子动力学和蒙特卡罗方法对氦泡形核和生长机制,比较了不同模拟条件下氦泡的演化机制。分析表明,晶界、位错、空位等内部缺陷和温度等外部条件都对氦泡的形核及其生长机制有影响。在此基础上提出了下一步研究方向和思路。     

钛中氦泡融合的分子动力学模拟

本文采用分子动力学方法模拟了金属钛中氦泡的融合,分析了氦泡融合对金属微结构的影响,对比了氦泡在金属块体内部与接近金属表面处融合的异同。研究表明:在金属块体内部,两氦泡的融合会在其周围诱发很多缺陷且范围逐渐扩大;直径均为1.77nm的两氦泡的融合会在二者周围形成位错环,位错环内金属原子的排列与基底的一致;两氦泡发生融合后由哑铃状向椭球形演化。在接近金属表面处,由氦泡融合诱发的缺陷易于向金属表面移动,氦泡周围的金属易于向晶体结构恢复;两氦泡发生融合后由哑铃状向半球形演化。     

钚自辐照老化过程中氦效应理论研究进展

钚因放射性衰变而出现自辐照老化效应。钚中氦行为是理解钚自辐照老化效应的一个基础和前提。运用分子动力学模拟技术，计算研究了钚中缺陷行为、氦与缺陷的相互作用、氦泡的初始形核过程、氦泡的长大过程以及氦泡对钚材料宏观性能的影响等。其中，钚-钚、钚-氦和氦-氦相互作用势分别采用修正嵌入原子多体势（modifiedembeddedatommethod，MEAM）、Morse对势和Lennard-Jones对势。主要的计算结果表明，氦原子与空位的结合能较大，在钚的自辐照过程中，两者易于结合并形成氦-空位团簇，成为氦泡的前驱体；氦泡可通过冲出位错环的机制而长大；氦泡的压力在GPa量级，且氦泡引起的基体膨胀很小。     

氚化钛膜中氦的热解吸行为初步研究

对He、Ti原子比n(He)/n(Ti)为0.004～0.300的7块氚化钛膜样品在1300K以下进行热解吸分析,以获得它们的热解吸谱。在低于1300K范围内,氚化钛膜共有4种氦的热释放峰,分别对应于贯穿至表面的氦泡、近表面的氦、体相中的氦泡和氦的小团簇。对这4种类型的氦释放峰的解吸温度和解吸量随膜中总氦量的变化分别进行分析,研究观测膜中各种状态存在的氦量随n(He)/n(Ti)增加的变化趋势。实验观测到,升温将导致氚化钛膜可容纳的氦量大幅降低。     

充氚不锈钢中氦行为的PAL和TEM研究

对充氚和未充氚的抗氢-2(HR-2)不锈钢样品进行退火处理,利用正电子湮没寿命谱(PAL)以及透射电镜(TEM)等技术探讨不锈钢中氦和微缺陷的相互作用。未充氚样品中,退火温度对缺陷态的影响主要表现为偏聚物在晶界的析出。充氚样品实验中,退火温度小于300℃时,充氚不锈钢中的He原子主要通过自捕获机制在晶内缺陷处聚集成泡;热处理温度为300～600℃时,充氚不锈钢中的He原子主要通过热迁移的方式迁移至晶界导致晶界宽化,但晶界处无明显的He泡形成;热处理温度大于600℃时,热平衡空位开始发挥作用,与聚集在晶内缺陷处的He原子结合形成He泡,且随退火温度的升高,He泡有明显聚合长大的现象。     

氚靶介绍

一、前言应用加速器中子源获得中子,常常是利用氘核、质子轰击含氚靶物质,进行核反应,产生快中子,这种作为靶子的含氚物质通常称为氚靶。随着科学技术的发展,氚靶在科学技术的许多领域中得到了广泛的应用,引起了人们的注意。根据应用及制备方法不同,氚靶可以分为气体靶、固体靶和金属氚化物靶。本文     

Korea's progress on the ITER tritium systems

Korea has been operating four units of CANDU nuclear power plant since 1983. Tritium generated in the heavy water of the plant has been removed by Wolsong TRF (tritium removal facility) since 2007. Korea has developed a 500-kCi BU-type tritium transport container. Furthermore, strictly controlled tritium release to the environment from the CANDU nuclear power plant in Korea will also be a helpful experience for ITER. The BU-type tritium transport container will be unpacked and the quantity of tritium in the metal tritides of the primary vessel will be measured accurately before the tritium is liberated by heating the metal tritides. In the ITER fuel cycle plant, Korea is responsible for the development and supply of the SDS (fuel storage and delivery system). We present the on-going R&D progress to use a non-nuclear material ZrCo for the storage and delivery of tritium. Especially we present the delivery characteristics of the ZrCo hydride bed by considering the fueling requirement and maintainability of the ZrCo hydride bed. We also present various test results for the experimental ZrCo beds and the test programs for the leak tight large scroll pump with a magnetic coupling-drive.     

Bubble nucleation process in a metal tritide modeled using a cellular automaton

The modeling of the ³He bubble nucleation phase that occurs during the aging of metal tritides such as palladium tritide is undertaken using a cellular automaton describing the material at the atomic scale. In that model, using simple rules of cell state change, the physical phenomena involved in the bubble nucleation, namely tritium diffusion, formation of ³He by radioactive tritium decay, ³He diffusion, ³He self-trapping, bubble growth, influence of pre-existing trapping sites such as vacancies, are taken into consideration. Calculations steps are related to physical time through the decay of tritium atoms into ³He atoms which is characterized by a half-life of 12.32 years.That work has shown that the bubble density and distribution are almost stable within a few days of aging – typically 5–10 –, whatever the input parameters, the system making created bubbles to grow thereafter instead of creating new ones. The reached bubble density is very dependent on the ³He mobility – related to temperature for instance – during the first days of aging. The smaller it is, the higher the density. With a larger density of trapping sites, bubbles appear earlier and their density is higher. These results are discussed and compared to available experimental and theoretical works on palladium tritide.     

金属氚化物中氦行为的研究现状与发展趋势

简要概述了近些年来金属氚化物中³He的存在和演化行为、延缓³He从材料中析出的可能途径以及时效对氚化物性能影响等方面的研究进展，重点对几种金属氚化物的³He时效行为进行了比较分析，并对其研究趋势作了概要评述。文章同时简要介绍了本研究组在金属氚化物³He演化行为研究方面的理论模拟和实验研究方面的工作进展。     

Helium bubbles formation in aluminum: Bulk diffusion and near-surface diffusion using TEM observations

Experimental and analytical investigation of helium bubble formation and growth in aluminum is presented. A pure aluminum with 0.15 wt% of ¹⁰B was neutron-irradiated in the Soreq nuclear reactor to get homogeneous helium atoms in the metal according to the reaction . Formation and growth of helium bubbles was observed in situ by heating the post-irradiated metal to 470 °C in TEM with a hot stage holder. It was found that above 400 °C the change in the bubble shape takes less than a second. In other experiments the Al-¹⁰B was first heated in its bulk shape and then observed in TEM at room temperature. In this case the helium bubble formation takes hours. Analytical evaluation of the diffusion processes in both cases was done to explain the experimental results. The number of helium atoms in a bubble was calculated from the electron energy loss spectrum (EELS) measurements. These measurements confirmed the hard sphere equation of state (EOS) for inert gases that was used in the analytical diffusion calculations.     

Design and analysis on tritium system of multi-functional experimental fusion–fission hybrid reactor (FDS-MFX)

As early application of fusion technology, the fusion–fission hybrid systems/reactors could be used to transmute long-lived radioactive waste and produce fissile nuclear fuel. A fusion–fission hybrid reactor named FDS-MFX was designated for checking and validating the DEMO reactor blanket relevant technologies. The reactor design is based on easy-achieved plasma parameters extrapolated from the successful operation of tokamaks and the subcritical blanket is designed based on the well-developed technologies of fission reactors. In this contribution, a concept of the tritium system was designed for the FDS-MFX: the tritium was extracted from LiPb by the helium purge gas which contains a small amount of hydrogen gas, then the impurity gas was removed by cold trap, finally tritium was separated from hydrogen isotope by the cryogenic distillation and supply to reactor core. On the basis of data obtained by present design and experimental research, the system parameters were presented and discussed in detail. The results preliminarily demonstrated the engineering feasibility of the design.     

Impact of nuclear irradiation on helium bubble nucleation at interfaces in liquid metals coupled to permeation through stainless steels

The impact of nucleating gas bubbles in the form of a dispersed gas phase on hydrogen isotope permeation at interfaces between liquid metals, like LLE, and structural materials, like stainless steel, has been studied. Liquid metal to structural material interfaces involving surfaces, may lower the nucleation barrier promoting bubble nucleation at active sites. Hence, hydrogen isotope absorption into gas bubbles modelling and control at interfaces may have a capital importance regarding design, operation and safety.He bubbles as a permeation barrier principle is analysed showing a significant impact on hydrogen isotope permeation, which may have a significant effect on liquid metal systems, e.g., tritium extraction systems. Liquid metals like LLE under nuclear irradiation in, e.g., breeding blankets of a nuclear fusion reactor would generate tritium which is to be extracted and recirculated as fuel. At the same time that tritium is bred, helium is also generated and may precipitate in the form of nano bubbles.Phenomena modelling is exposed and implemented in openFROM^® CFD tool for 0D to 3D simulations. Results for a 1D case show the impact of a He dispersed phase of nano bubbles on hydrogen isotopes permeation at an interface. In addition, a simple permeator simulation, consisting in a straight 3D pipe is exposed showing the effect of a He dispersed gas phase on hydrogen isotope permeation through different stainless steels. Results show the permeation reduction as a function of the interface area covered by He bubbles.Our work highlights the effect of gas bubble nucleation at interfaces and the importance of controlling these phenomena in nuclear technology applications.     

聚变-裂变混合堆水冷包层中子物理性能研究

研究直接应用国际热核聚变实验堆（ITER）规模的聚变堆作为中子驱动源，采用天然铀为初装核燃料，并采用现有压水堆核电厂成熟的轻水慢化和冷却技术，设计聚变-裂变混合堆裂变及产氚包层的技术可行性。应用MCNP与Origen2相耦合的程序进行计算分析，研究不同核燃料对包层有效增殖系数、氚增殖比、能量放大系数和外中子源效率等中子物理性能的影响。计算分析结果显示，现有核电厂广泛使用的UO₂核燃料以及下一代裂变堆推荐采用的UC、UN和U₉₀Zr₁₀等高性能陶瓷及合金核燃料作为水冷包层的核燃料，都能满足以产能发电为设计目标的新型聚变 裂变混合堆能量放大倍数的设计要求，但只有UC和U₉₀Zr₁₀燃料同时满足聚变燃料氚的生产与消耗自持的要求。研究结果对进一步研发满足未来核能可持续发展的新型聚变-裂变混合堆技术具有潜在参考价值。     

Confirmatory experiments for nuclear emissions during acoustic cavitation

Confirmatory experiments were conducted to assess the potential for nuclear fusion related emissions of neutrons and tritium during neutron-seeded acoustic cavitation of deuterated acetone. Corresponding control experiments were conducted with normal acetone. Statistically significant (5–11S.D. increased) emissions of 2.45 MeV neutrons and tritium were measured during cavitation experiments with chilled deuterated acetone. Control experiments with normal acetone and irradiation alone did not result in tritium activity or neutron emissions. Insights from imaging studies of bubble clusters and shock trace signals relating to bubble nuclear fusion are discussed.