吴攀老师加入了由国际原子能机构（IAEA）组织的共同合作项目（CRPI31034），该项目的宗旨是为设计超临界水堆原型堆开展先进热工水力模型和预测工具展开研究工作，吴攀老师将负责系统分析程序SCTRAN的改进工作，合作周期三年。

       2022年9月1日-2日，该CRP举行了线上开题会，来自十余个国家的专家开展了18个专题报到。吴攀老师做题为《Upgrading and Validation of System Analysis Code for SCWR-SCTRAN》的报告。

Summary of the CRP

There is a strong interest in Super-Critical Water cooled Reactor (SCWR) designs among the Member States beyond the current fleet of water cooled reactors for electricity production and non-electric applications and to contribute to climate change mitigation. Several conceptual designs of SCWR have been developed to generate greater than 1000 MWe in Canada, China, European Union, Japan and the Russian Federation. In addition, the development has been expanded to include the designing of super-critical small modular reactors (SCSMR) for generating capacity of up to 350 MWe, which can also be adopted as prototypes for the reference SCWR design. The design process requires advances in key technology areas such as neutronics, fuel, materials, chemistry, thermal-hydraulics, control and safety. Thermalhydraulics is one of the remaining critical areas important for maintaining coolability of the fuel and hence safe operation of the reference and prototype SCWRs. A significant amount of thermal-hydraulics studies was performed to support design, licensing and operation of the current fleet of nuclear reactors operating at subcritical pressures. However, information and experimental data remain scarce on thermal-hydraulics behaviours for fluids at supercritical pressures. The objective of this CRP is to therefore, establish a coherent body of knowledge about fluids at supercritical pressures and/or temperatures needed to prototype the SCWR designs. This is an ambitious goal, which can be achieved only with a renewed effort in research and development (R&D) that identifies and closes current gaps in technology areas as well as enhances knowledge and technological bases relevant to design options. Achieving this goal would also enhance the knowledge basis in similarity to the level of availability in water cooled reactor technologies at subcritical pressures. The scope of the CRP is the advancement of predictive tools (such as correlations, system and sub-channel codes) and models supported by computational fluid dynamics (CFD) tools, based on improved knowledge and understanding of thermal-hydraulics phenomena, for the design and operation of SCWR prototypes. This CRP will bring together experts from Member States with water cooled reactor technologies to utilize, test and further improve modelling tools. Predictive capability of these tools will be assessed against experimental data or benchmarked against other tools. The associated research activities will foster national excellence and international cooperation, promote sharing of newly developed knowledge, and contribute to capacity building in developing countries. Completing activities covered in this CRP would provide improved predictive tools to Member States for design and operation of SCWRs and prototypes. These tools could also be applied for licensing and operation of the current fleet of nuclear reactors. Participating in this CRP would enhance the R&D capability and infrastructure (such as system and subchannel codes), as well as facilitate training of highly qualified personnel for the nuclear industry in both developed and developing Member States. In addition, the newly developed knowledge to be shared with Member States through various activities, will be as well aimed at supporting the graduate students and broaden the representation of female graduates in the field.