Properties of new-type liquid tritium breeders and advanced liquid blanket design

新型液态氚增殖剂性能及先进液层设计

• 批准号: 14380217
• 负责人: TERAI Takayuki
• 金额: $ 9.47万
• 依托单位: The University of Tokyo
• 依托单位国家: 日本
• 项目类别: Grant-in-Aid for Scientific Research (B)
• 财政年份: 2002
• 资助国家: 日本
• 起止时间: 2002 至 2005
• 项目状态: 已结题
• 来源: https://kaken.nii.ac.jp/grant/KAKENHI-PROJECT-14380217/
• 关键词: fusion reactor; liquid blanket; breeding material; lithium-tin; fluoride molten salt; tritium; diffusion coefficient; solubility; リチウム-スズ; 核融合炉液体; ブランケット; フッ化物; 溶融塩; 中性子高温照射; 設計

Establishment of fusion fuel cycle is essential in order to realize D-T fusion reactor system, in which more amount of tritium should be produced in the blanket than that of tritium consumed for D-T reaction. The research and development for liquid blanket is more delayed than that of solid blanket, though the former one has a potential of charming concept from the point of economic efficiency. In this study, essential data for liquid breeder properties were obtained and some advanced blanket concepts are reviewed by using them. In particular, liquid lithium-tin alloy, the reduction-oxidation control of fluoride molten salt and the property data of other liquid breeders were supplemented in order to compare all the liquid breeder candidates. New liquid blanket concepts were discussed with the data, and the feasibility and the critical issues were clarified.The following tasks were accomplished;(1) Basic properties such as thermal properties, density and phase diagram of lithium-tin liquid alloy were measured. The tritium release properties such as tritium diffusivity and tritium solubility of the alloy were obtained under neutron irradiation at high temperature by using a blanket-simulated system installed in the fast neutron source reactor "YAYOI".(2) Reduction experiments for HF in fluoride molten salt (LiF-BeF_2) were demonstrated using beryllium as a reducing agent dipped in the salt. Compatibility of structural materials with the reduced fluoride molten salt was investigated and the feasibility of this method was confirmed.(3) Development of Er_2O_3 insulating ceramic coating was done.(4) Evaluation of the data obtained in this study and the discussion on the application to the advanced blanket design were carried out.

为了实现D-T聚变反应堆系统，必须建立聚变燃料循环，在该系统中，包层中产生的氚量应大于D-T反应所消耗的氚量。液体包层虽然从经济效益的角度看具有诱人的概念潜力，但其研究和开发比固体包层要滞后得多。本研究获得了有关液体增殖剂性质的基本数据，并利用这些数据对一些先进的包层概念进行了评述。特别是补充了液态锂锡合金、氟化物熔盐的氧化还原控制以及其他液体增殖剂的性能数据，以便对所有液体增殖剂候选者进行比较。本文主要完成了以下工作：（1）测定了锂锡液态合金的热性能、密度和相图等基本性质。利用快中子源反应堆“YAYOI”中的包层模拟系统，在高温中子辐照下，获得了合金的氚扩散率和氚溶解度等氚释放特性。(2)以铍为还原剂，在氟化物熔盐（LiF-BeF_2）中进行了HF的还原实验。研究了结构材料与还原氟化物熔盐的相容性，证实了该方法的可行性。(3)研制了Er_2O_3绝缘陶瓷涂层。(4)对本研究中获得的数据进行了评价，并讨论了在先进包层设计中的应用。

项目成果

Measurements of Tritium Properties in Li_20Pb_80 Alloy

Li_20Pb_80合金中氚性能的测定

• 发表时间: 2005
• 期刊: Proceedings of the 8^th Japan-China Symposium on Materials for Advanced Energy Systems and Fission & Fusion Engineering
• 作者: Yi Kang;Takayuki Terai
• 通讯作者: Takayuki Terai

In-Reactor Tritium Release Behavior from Molten Lithium-Tin Alloy as a Liquid Metal Breeder

作为液态金属增殖剂的熔融锂锡合金的反应堆内氚释放行为

• 发表时间: 2003
• 期刊: Materials for Advanced Energy systems and Fission & Fusion Engineering(Z.G.Wang et al.ed.)(World Scientific)
• 作者: Yi Kang;Takayuki Terai;et al.
• 通讯作者: et al.

Progress in coating development for fusion systems

• DOI: 10.1016/s0920-3796(02)00291-0
• 发表时间: 2002-11
• 期刊: Fusion Engineering and Design
• 影响因子: 1.7
• 作者: D. L. Smith;J. Park;I. Lyublinski;V. Evtikhin;A. Perujo;H. Glassbrenner;T. Terai;S. Zinkle

Mass-Transport Properties to Estimate Rates of Tritium Recovery from Flibe Blanket

用传质特性来估计 Flibe 覆盖层中氚回收率

• 发表时间: 2002
• 期刊: Fusion Science and Technology 41
• 作者: S.Fukada;M.Nishikawa;A.Sagara;T.Terai
• 通讯作者: T.Terai

Carbon tiles as spectral-shifter for long-life liquid blanket in LHD-type reactor FFHR

碳瓦作为 LHD 型反应堆 FFHR 中长寿命液层的光谱变换器

• 发表时间: 2006
• 期刊: Fusion Engineering and Design Vol.81
• 作者: T.-H. Watanabe;H. Sugama;洲鎌 英雄;A.Sagara et al.
• 通讯作者: A.Sagara et al.