Advanced study of tritium recovery from molten salt Flibe blanket in fusion reactor

聚变反应堆熔盐Flibe包层回收氚的最新研究

基本信息

批准号：
14380220
负责人：
FUKADA Satoshi
金额：
$ 4.8万
依托单位：
Kyushu University
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 2004
项目状态：
已结题

项目摘要

Flibe (2LiF+BeF_2 mixed molten salt) is expected to be an advanced liquid blanket fluid for a helical-type DEMO fusion reactor called FFHR-2 because it has an ability of good thermal conductance and high tritium breeding ratio under high magnetic field and high-density neutron flux. However, it has disadvantages that it is difficult to handle tritium in the molten salt because of generation of tritium fluoride and the recovery and enclosure of tritium are difficult. Therefore, there was less application to conceptual design of fusion reactors and therefore less experimental studies on Flibe/tritium chemistry. In the present study, we investigated experimentally the permeability of hydrogen isotopes through Flibe and reduction-oxidation (redox) control by Be rods immersed in Flibe that will provide important data to design fusion reactors. The main purpose of the present study is to propose a new blanket circulation loop system composed of Flibe ducts, a tritium extraction system and a … More heat exchanger that can control to a rate lower than 10 Ci/day of acceptable tritium leak rate and a tritium concentration lower than 1 ppm of acceptable tritium inventory. The following findings were obtained from the experiment and analysis of the present study :1.We determined the permeability of deuterium through molten Flibe enclosed in a dual-tube Ni permeation vessel. Judging from the permeability, diffusivity and solubility of deuterium in Flibe, hydrogen isotopes are resent as a H^+ ion in Flibe. Therefore strong interaction between H^+ and F^- ions was observed, and HF (DF or TF) is a main species diffusing in non-redox controlled Flibe.2.We determined hydrogen H_2 through Flinak (a LiF+NaF+KF mixed molten salt), and hydrogen was present as a molecular form in it. This is because there is no tetragonal network of BeF_4^<2-> different from the Flibe case. F^- ions in Flinak were localized in the vicinity of Li^+, K^+ and Na^+ ions. In other words, there are much less free F^- ions in Flinak, and therefore Flinak corresponds to the well redox-controlled Flibe.3.Flibe was successfully redox-controlled by Be immersed in it. This is because free F- ions that were present in non-controlled Flibe were changed to BeF_2 by the reaction with Be dissolved in Flibe physically. The free F^- ions were consumed by the redox reaction and hydrogen in Flibe was present in a molecular form. Consequently, tritium will be present in a molecular form in well redox-controlled fusion reactor blankets when Be is used as a neutron multiplier.4.In order to maintain the tritium leak rate in a 1GW fusion reactor lower than the acceptable level (10 Ci/day), we need a sophisticated tritium recovery system made of low permeable materials. We provided design equations for tritium permeable window, bubbling tower and spray tower for high tritium recovery, and each apparatus was designed using the equations. Less

FLIBE（2LIF+BEF_2混合熔融盐）预计将是一种称为FFHR-2的螺旋型演示融合反应器的晚期液体毯液，因为它具有良好的导热电导能力和高磁场下高磁场和高密度中性通量的能力。但是，由于产生氟化tri含量，很难处理熔融盐中的tri虫，而且很难处理tri含量的缺点。因此，在融合反应堆的概念设计上的应用较少，因此对FLIBE/Tritium Chemistry的实验研究较少。在本研究中，我们通过FLIBE和减少氧化（氧化还原）控制液体通过浸入FLIBE中的FLIBE进行了实验研究，将氢同位素的渗透率（氧化还原）控制（氧化还原）控制，这将为设计融合反应器提供重要的数据。本研究的主要目的是提出一个由Flibe管道，一个提取系统组成的新毯子循环循环系统，以及……更多的热交换器，可以控制低于10 CI/天的速率/天泄漏率的10 CI/天，而tri液浓度低于可接受的tripium coneting的1 ppm。从本研究的实验和分析中获得了以下发现：1。我们确定了氘中通过熔融液体封闭在双管Ni渗透容器中的渗透性。从氘中氘的渗透性，扩散性和溶解度来看，氢同位素在FLIBE中是一种h^+离子的不满。因此，观察到H^+和F^ - 离子之间的强相互作用，HF（DF或TF）是非氧化物受控的FLIBE中的主要物种。2。我们确定了通过Flinak（一种LIF+NAF+KF混合熔融盐）确定氢H_2，并且在其中以分子形式存在氢。这是因为与Flibe情况不同的BEF_4^<2->没有四方网络。弗林纳克（Flinak）中的f^ - 离子位于li^+，k^+和na^+离子附近。换句话说，弗林纳克（Flinak）中的自由f^ - 离子要少得多，因此弗林纳克（Flinak）对应于氧化还原良好的控制flibe。3.Flibe被浸入其中成功地控制了氧化还原。这是因为通过与反应的反应将其溶解在flibe中。自由f^ - 离子被氧化还原反应消耗，并以分子形式呈现Flibe中的氢。因此，当用作中子乘数时，tri虫将以分子形式存在于氧化还原良好的控制融合反应器毯中。4。为了将tile液泄漏速率保持在1GW融合反应器（10 ci/day）的1GW融合反应器中，我们需要由低渗透量的低渗透率制成的复杂的基本回收系统。我们为Tritium渗透的窗户，气泡塔和喷塔提供了设计方程，以进行高trium恢复，并且每个设备都是使用方程式设计的。较少的