Development of Accurate/Advanced Radiotherapy Treatment Planning and Quality Assurance System (ARTS)

A prototype of accurate/advanced radiotherapy treatment planning and quality assurance system (ARTS) is developed and key technical issues related to the improvement of the treatment accuracy is studied. After a brief introduction to the prototype of ARTS, the advanced development in key technical issues is presented, including image data processing and human body modeling, fast and accurate hybrid dose calculation, multi-objective optimization of inverse planning, intelligent patient positioning, and dose verification.     

磁约束聚变堆及ITER实验包层模块设计研究进展

目前国际上代表性的磁约束聚变反应堆设计包括美国的ARIES系列和APEX系列、欧洲的PPCS系列、日本的SSTR系列、中国的FDS系列设计,以及国际合作的国际热核聚变实验堆等。这些设计研究涉及到聚变能科学技术发展的各个方面,包括聚变实验堆、商用示范堆和商用动力电站等的设计研究、相关物理和技术发展以及相关的能源技术与经济策略研究等。简要介绍了上述设计研究领域的现状和发展趋势。The uhimate goal of the fusion program is to develop large scale power plants for the production of electricity. At present, there are many representative designs of magnetic confinement fusion reactors in the world,e.g. ARIES and APEX in USA, PPCS in EU, SSTR in Japan, FDS in China, and International Thermonuclear Experimental Reactor （ITER）. These studies cover many aspects on fusion experimental reactors, DEMO reactors, and commercial fusion power plants, including plasma physics, blanket technologies, material behavior, and technologies required to construct and operate such complex plants. The study status and development strategy in various countries are summarized and reviewed.     

CLAM钢冲击和拉伸性能测试与研究

对中国低活化马氏体钢——CLAM钢的冲击和拉伸性能进行了测试。结果表明:CLAM钢的塑。脆转变温度在-100℃左右,低于国际上其它几种典型的低活化马氏体钢;在室温和600℃时抗拉强度分别为668和334MPa,类似于EUROFER97的性能。约8μm的晶粒尺寸是CLAM钢具有较好冲击和拉伸性能的主要原因之一。The impact and tensile tests were carried out on the China Low Activation Martensitic steels （CLAM）. The results show: the Ductile-Brittle Transition Temperature （DBTY） is about - 100 ℃, which is lower than those of some other RAFMs; The ultimate strength are 668 MPa at room temperature and 334 MPa at 600℃, which are comparable to those of EUROFER97. The finer grain size of about 8 μm was considered as one of reasons for the superior mechanical properties of CLAM.     

Study of aluminum coating prepared by PVD used as anti-corrosion in liquid lead-bismuth

Liquid metals-such as lead （Pb） or lead-bismuth （PbBi） are used as reactor core coolants for accelerator driven systems （ADS） proposed for high-level radioactive waste transmutation. Compatibility of steels with liquid PbBi is a key problem because steels are attacked by dissolution of the components in PbBi, so it has to form a stable coating on steel surface. There are many methods to prepare anti-corrosion coatings on steel, such as hot dipping, pack cementation, plasma spaying, and physical vapor deposition （PVD）. Compared with other methods, the PVD method is easy to control the thickness of the coating and the obtained coatings are dense which is crucial to the anti-corrosion ability of the coatings. In this letter, PVD aluminum coatings are developed on the surface of T91 steel and different heat-treatment atmosphere is used to adjust the microstructure, aluminum content, and the phase of the coatings. It is found that the coatings have good adherence ability with steel. The aluminum content and the phase of the coating can be adjusted by the heat-treatment atmosphere. Corrosion tests are performed in oxygen-saturated liquid PbBi at 550 ℃ for 1 000 h, the phase and composition of the coating do not change drastically. All the results indicate that the PVD is a useful method to prepare coatings on the surface of steel used in liquid PbBi.     

Activation Characteristics of Fuel Breeding Blanket Module in Fusion Driven Subcritical System

Shortage of energy resources and production of long-lived radioactivity wastes from fission reactors are among the main problems which will be faced in the world in the near future. The conceptual design of a fusion driven subcritical system (FDS) is underway in Institute of Plasma Physics, Chinese Academy of Sciences. There are alternative designs for multi-functional blanket modules of the FDS, such as fuel breeding blanket module (FBB) to produce fuels for fission reactors, tritium breeding blanket module to produce the fuel, i.e. tritium, for fusion reactor and waste transmutation blanket module to try to permanently dispose of long-lived radioactivity wastes from fission reactors, etc. Activation of the fuel breeding blanket of the fusion driven subcritical system (FDSFBB) by D-T fusion neutrons from the plasma and fission neutrons from the hybrid blanket are calculated and analysed under the neutron wall loading 0.5 MW/m2 and neutron fluence 15 MW.yr/m2. The neutron spectrum is calculated with the worldwide-used transport code MCNP/4C and activation calculations are carried out with the well known European inventory code FISPACT/99 with the latest released IAEA Fusion Evaluated Nuclear Data Library FENDL-2.0 and the ENDF/B-V uranium evaluated data. Induced radioactivities, dose rates and afterheats, etc, for different components of the FDS-FBB are compared and analysed.     

医用放射性同位素99Mo/99mTc生产现状和展望

99mTc是目前临床诊断应用最为广泛的医用放射性同位素。现有医用99mTc主要通过在实验堆中辐照高浓缩235U生成的99Mo衰变得到,存在工艺复杂、成本高、长距离运输损失等弊端以及核扩散风险。此外,全球实验反应堆为数不多且面临老化、退役问题,也多次因计划内的维修或意外停产事件而使99mTc供应面临困难。本文从99Mo/99mTc的供求现状入手,分析了目前供应链中存在的主要问题,重点介绍了六种传统及新型99Mo/99mTc生产技术的原理、研究进展及其经济性效益。详细评述了三种99Mo/99mTc分离纯化工艺,提出了99Mo/99mTc生产的发展趋势和展望。其中,以加速器驱动裂变低浓缩铀盐溶液的生产方式具有无反应堆、无高浓缩铀、放射性废物少等优势,是未来的重点研究方向。同时,为减少99Mo/99mTc损失,提高产品质量,开发和优化与生产体系相适应的分离纯化工艺也势在必行。中国科学院核能安全技术研究所FDS中科凤麟核能团队设计开发的一种氘氚聚变中子源驱动的99Mo次临界生产系统方案,可获得27Ci/d的99Mo产量,能满足国内一个中等省份的医疗诊断需求。