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首页> 外文会议>Proceedings of the 9th China-Japan Symposium(CJS-9) on Materials for Advanced for Energy Systems and Fission amp; Fusion Engineering Jointed with CAS-JSPS Core-university Program Seminar on Fusion Materials, System and Design Integration >Deuterium Desorption Behavior of Solid Tritium Breeding Material, Lithium Titanate
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Deuterium Desorption Behavior of Solid Tritium Breeding Material, Lithium Titanate

机译：固体Tri繁殖材料钛酸锂的氘解吸行为

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摘要

In a solid breeder blanket cooled by water, pellets of Li<,2>TiO<,3> will be employed as tritium breeding material. Structure material in this blanket is low activation ferritic steel, F82H. The operation temperature is limited below approximately 820K owing to swelling caused by neutron irradiation. Tritium produced by fusion neutrons in this breeding material has to be desorbed under a blanket operation for tritium inventory to be small. The blanket module, however, has a spatial distribution of temperature. Thus, the tritium desorption behavior has to be clarified in order to make a scheme for tritium recovery. In the present study, a solid breeding material, Li <,2>TiO<,3>, was irradiated by 1.7keV deuterium ions, and an amount of retained deuterium and deuterium desorption behavior were investigated using a thermal desorption spectroscopy. Dependence of deuterium fluence on amount of retained deuterium was also obtained. In order to examine trapping mechanisms of deuterium in Li<,2>TiO<,3>, similar experiments were conducted for Li and Ti films Deuterium implanted to Li<,2>TiO<,3> desorbed in forms of HD, D<,2>, HDO and D<,2>O. The desorption peak appeared at 500-600K, but significant desorption up to 900K was observed. The range of temperature in the lithium titanate of the blanket module is assumed from 600K to 1200K. These results suggest that the tritium produced in the blanket is partly not desorbed. Thus, the spatial distribution of temperature in the blanket has to be controlled for the tritium to be desorbed during the operation. The desorption spectra of deuterium in Li<,2>TiO<,3> were similar to those of Li. This suggests that most of implanted deuterium is trapped in forms of Li-D and Li-OD. Based upon the present results, a tritium inventory and a suitable design for the blanket module are discussed.
机译：在用水冷却的固体育种毯中，将Li 2 TiO 3的粒料用作tri育种材料。该橡皮布中的结构材料是低活化铁素体钢F82H。由于中子辐照引起的膨胀，工作温度被限制在大约820K以下。聚变中子在这种繁殖材料中产生的必须在毯式操作下解吸，以使inventory的存量变小。但是，橡皮布模块具有温度的空间分布。因此，必须弄清楚the的解吸行为，以便制定recovery的回收计划。在本研究中，用1.7keV氘离子辐照了固体繁殖材料Li 2，TiO <，3>，并使用热脱附光谱研究了保留的氘量和氘的脱附行为。还获得了氘通量对保留氘量的依赖性。为了检查氘在Li 2 TiO 3中的俘获机理，对Li和Ti膜进行了类似的实验，将氘注入以HD，D <形式解吸的Li 2 TiO 3中注入了氘。 ，2>，HDO和D <2> O。解吸峰出现在500-600K，但观察到高达900K的显着解吸。橡皮布模块的钛酸锂的温度范围假定为600K至1200K。这些结果表明，毯子中产生的the没有部分解吸。因此，必须控制毯子中温度的空间分布，以使operation在操作过程中解吸。 Li 2 TiO 3中的氘的解吸光谱与Li相似。这表明大多数植入的氘以Li-D和Li-OD的形式被捕获。基于目前的结果，讨论了inventory库存和毯式模块的合适设计。

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