In this review paper on heavy ion inertial fusion (HIF), the state-of-the-art scientific results are presented and discussed on the HIF physics, including physics of the heavy ion beam (HIB) transport in a fusion reactor, the HIBs-ion illumination on a direct-drive fuel target, the fuel target physics, the uniformity of the HIF target implosion, the smoothing mechanisms of the target implosion non-uniformity and the robust target implosion. The HIB has remarkable preferable features to release the fusion energy in inertial fusion: in particle accelerators HIBs are generated with a high driver efficiency of ~30%-40%, and the HIB ions deposit their energy inside of materials. Therefore, a requirement for the fusion target energy gain is relatively low, that would be ~50-70 to operate a HIF fusion reactor with the standard energy output of 1 GWof electricity. The HIF reactor operation frequency would be ~10-15 Hz or so. Several-MJ HIBs illuminate a fusion fuel target, and the fuel target is imploded to about a thousand times of the solid density. Then the DT fuel is ignited and burned. The HIB ion deposition range is defined by the HIB ions stopping length, which would be ~1 mm or so depending on the material. Therefore, a relatively large density-scale length appears in the fuel target material. One of the critical issues in inertial fusion would be a spherically uniform target compression, which would be degraded by a non-uniform implosion. The implosion non-uniformity would be introduced by the Rayleigh-Taylor (R-T) instability, and the large densitygradient- scale length helps to reduce the R-T growth rate. On the other hand, the large scale length of the HIB ions stopping range suggests that the temperature at the energy deposition layer in a HIF target does not reach a very-high temperature: normally about 300 eV or so is realized in the energy absorption region, and that a direct-drive target would be appropriate in HIF. In addition, the HIB accelerators are operated repetitively and stably. The precise control of the HIB axis manipulation is also realized in the HIF accelerator, and the HIB wobbling motion may give another tool to smooth the HIB illumination non-uniformity. The key issues in HIF physics are also discussed and presented in the paper.

等离子体排灰气处理系统是聚变反应装置氘氚燃料循环系统中极为重要的环节。该系统的主要功能是从反应后的排灰气中回收剩余的氘氚燃料, 并处理壁材料净化、系统维护等非正常运行模式以及分析与辅助系统中产生的含氚杂质气体。介绍了国际上聚变堆等离子体排灰气的组成和主要处理工艺, 简述了钯膜分离、膜反应及催化反应-膜分离、电解反应、分解反应及氧化-分解等各关键单元技术的基本原理和研究进展, 并进行了分析和评价, 提出了目前国内在该领域需要开展的研究工作。

将LiAlO2陶瓷小球置于裂变反应堆中辐照, 采用热解吸技术研究该类产氚材料的堆外放氚特性, 考察了升温速率、载气组分、催化活性元素和提氚温度对氚释放行为的影响；采用电子自旋磁共振(ESR)实验技术研究了辐照缺陷的顺磁特征。结果表明:LiAlO2中氚的扩散速度慢, 热解吸活化能高, 氚释放主要分布在750~1000 K；表面氢同位素交换反应贡献大, 释氚形态受载气条件的影响较大, 当氦气中添加H2时, 会增大HTO转化成HT的比例；中子辐照会在LiAlO2中诱生F+,O-和O2-等缺陷色心, 其退火湮灭行为与氚释放过程存在一定关系。

研究了块体金属玻璃（块体非晶合金）Zr65Al7.5Ni10Cu17.5, Co61.2B26.2Si7.8Ta4.8和金属多晶钼3种第一镜材料经低温等离子体H和Ar辐照后的表面特性变化。结果表明，两种块体金属玻璃的抗H等离子体溅射能力与其成分有关。随着等离子体辐照时间的增加，金属多晶钼和块体金属玻璃Zr65Al7.5Ni10Cu17.5的表面粗糙度增大,镜面反射率降低；而块体金属玻璃Co61.2B26.2Si7.8Ta4.8的表面粗糙度减小,镜面反射率升高。X射线衍射仪（XRD）分析表明，块体金属玻璃在离子体溅射过程中，表面微结构具有自修复性。