摘要：The International Thermonuclear Experimental Reactor （iter） feeder procurement is now well underway. The feeder design has been improved by the feeder teams at the iter organization （IO） and the Institute of Plasma Physics, Chinese Academy of Sciences （ASIPP） in the last 2 years along with analyses and qualification activities. The feeder design is being progressively finalized. In addition, the preparation of qualification and manufacturing are well scheduled at ASIPP. This paper mainly presents the design, the overview of manufacturing and the status of integration on the iter magnet feeders.

摘要：The cryostat is a vacuum tight container enveloping the entire basic systems of the iter tokamak machine,including a vacuum vessel,a superconducting magnet and thermal shield *** is evacuated to a pressure of 10^-4Pa to limit the heat transfer via gas conduction and convection to the cryogenically cooled *** important function of cryostat is to support all the loads from the tokamak to the concrete floor of the pit by its support system during different operational regimes and accident *** paper briefly presents the design evolution and associated analysis of the cryostat support system and the structural interface with the building.

摘要：A conceptual design review of the iter gas injection system （GIS） function, safety, operation, and maintenance has recently been successfully completed. The GIS design can now continue to the preliminary design stage. This paper gives an overall description of the requirements and implementation at the concept design level. The designs of the sub-systems according to its breakdown structure are discussed against the corresponding requirements.

摘要：The iter Gas Injection System（GIS） plays an important role on fueling, wall conditioning and distribution for plasma operation. Besides that, to support the safety function of iter, GIS needs to implement three nuclear safety Instrumentation and Control（I＆C） *** this paper, these three functions are introduced with the emphasis on their latest safety classifications. The nuclear I＆C design concept is briefly discussed at the end.

摘要：In Tokomak, the support of the ELM coil, which is close to the plasma and subject to high radiation level, high temperature and high magnetic field, is used to transport and bear the thermal load due to thermal expansion and the alternating electromagnetic force generated by high magnetic field and AC current in the coil. According to the feature of iter ELM coil, the mechanical performance of rigid and flexible supports under different high nuclear heat levels is studied. Results show that flexible supports have more excellent performance in high nuclear heat condition than rigid supports. Concerning thermal and electromagnetic （EM） loads, optimized results further prove that flexible supports have better mechanical performance than rigid ones. Through these studies, reasonable support design can be provided for the ELM coils or similar coils in Tokamak based on the nuclear heat level.

摘要：针对iter中国氦冷固态增殖剂试验包层模块(HCCB TBM)的概念设计方案进行了初步中子学设计和优化。在铍球床填充率从80%降为62%的情况下,通过调整TBM内部结构的材料和布置,提出了一种中子学性能更好且满足安全要求的设计方案。计算结果表明,优化后HCCB TBM的产氚率比概念设计值提高的满功率运行一天后的产氚量为0.42mg,但总核热和最大功率密度有了一定降低。

摘要：基于中国氦冷固态增殖剂试验包层模块(CN HCCB TBM)的最新设计方案和iter提供的中子学基准模型C-lite,采用国际通用的Monte Carlo粒子输运程序MCNP和欧洲活化程序FISPACT-2007对HCCB TBM及其辅助系统(统称为HCCB TBS)进行了详细的活化计算分析,得到并讨论了各结构部件的放射性、余热和接触剂量率结果。结果表明,停堆时HCCB TBM模块的总放射性和总余热分别为2.348×1016 Bq和5.826 k W。活化计算结果可以为TBS的安全分析、维护和放射性废物处置等提供数据基础和分析依据。