1. Research fields The research of the Division of Reactor Structure (Division 104) is based on the high temperature gas-cooled reactors, heating reactors and high flux reactors, designed and developed by INET. Its scientific research fields are focused on the R&D of key components of the reactors, as well as nuclear safety-grade systems and circuits. The main research fields include: (1) Reactor pressure vessels; (2) HTGR inner components including metal, graphite and carbon bricks; PWR inner components; (3) Heat exchangers and steam generators; (4) Nuclear piping systems, including first- and second-loops , nuclear safety grade pumps and valves; (5) New control rod drive system. Research directions include: (1) Structural optimization of the design of reactor systems and components; (2) Integrity assessment of pressure vessels; (3) Pre-breakage leakage analysis technology for pressure vessels and pipelines; (4) Performance study and life assessment of graphite structural materials for reactors; (5) Research on the seismic performance of bulk structures; (6) Research and development of new heat exchanger and steam generator systems; (7) Soil-structure interaction and floor reaction spectrum generation technology; (8) Mechanical analysis technology for large-scale structures; (9) Research on rapid numerical analysis technology for large-scale flow and heat transfer; (10) Seismic analysis technology for components and systems; (11) Research on fluid-induced vibration; (12) Particle dynamics of graphite in HTGRs; (13) Research on analysis technology for key equipment of new-generation PWR NPPs; (14) Computer-aided design (CAD) of engineering structures; (15) R&D of new control rod drive system, etc..
2. Research Projects The Division of Reactor Structure carries out research activities mainly focusing on HTGR and low-temperature NHR developed by INET, and lays a solid foundation for the research and development of these two new types of reactors.
3. Research Facilities The research of the Division is mainly focused on R&D of nuclear safety equipment and systems. According to the requirements of nuclear safety regulations, a large number of calculations and analyses need to be carried out for all kinds of equipment and systems. In order to meet the demands of scientific research, the Division has gradually equipped itself with a complete set of structural and thermal calculation softwares, which are mainly commercial softwares of international renown. These analysis softwares basically meet the technical requirements of mechanical analysis of equipment structure, piping system analysis, thermal analysis, multi-system coupling analysis and other aspects. While constructing the software system, the Division has also provided good computer conditions to ensure an outstanding application platform for the software system. At present, each researcher of the Division owns a high-performance microcomputer. At the same time, the Division is also specially configured with two IBM servers and an integrated blade server, which are specially used for large-scale analyses and calculations. In order to cooperate with these servers to carry out large-scale calculations, there are also three sets of high-performance HP workstations for prior and post processing of the calculations. The above hardware and software conditions have guaranteed that the Division has sufficient capacities to carry out large-scale structural statics and dynamics analyses, highly nonlinear structural mechanics analyses, thermal analyses, multi-physics field coupling analyses, fracture mechanics and structural reliability analyses, and analyses of fluid transport systems. At present, the Division has realized the organic combination of research, design and calculation, which improves the working efficiency and design level, reduces the interference of human factors, and provides excellent technical guarantee for the achievement of R&D objectives.
HTR-PM first-loop pressure boundary finite element analysis (triple shell and its support)	HTR-PM evaporator full-size heat transfer unit test loop
Load tests for graphite and carbon inner component models	Finite element analysis evaluation of graphite and carbon inner components
4. Academic Achievements Main Awards The 5MW Nuclear Heating Reactor (NHR-5) and the 10 MW High Temperature Gas-cooled Test Reactor (HTR-10) built in the last century are the achievements of many years of scientific research and development of the Division. The projects have won numerous national awards, which were awarded to several members of the Division. (1) In 2022, the First Prize of Scientific and Technological Progress of the China Nuclear Energy Association: Research on the Manufacturing Technology and Engineering Application of High Temperature Gas-cooled Reactor Steam Generator (2) In 2021, Scientific and Technological Achievement Award of Chinese Nuclear Society: Thermo-Hydraulic and Engineering Verification Tests of High Temperature Gas-Cooled Reactor Spiral Tube DC Steam Generator (3) In 2020, Second Prize of Shanghai Science and Technology Progress: The World's First 200WM High Temperature Gas-Cooled Nuclear Reactor Pressure Vessel with Independent Intellectual Property Rights (4) In 2019, First Prize of Jiangsu Provincial Scientific and Technological Progress: Development and Industrialization of Key Tubes and Core Components for Advanced Nuclear Energy System (5) Outstanding Thesis Awards for Key Laboratories of the Ministry of Education, 7 people
Recent publications (1) 79 articles in international core journals (2) 30 articles in domestic core journals, including 71 articles in SCI and 33 articles in EI. (3) 28 articles in international conferences, and 24 teachers participated in international academic exchanges. (4) 34 articles in domestic conferences, 25 teachers participated in domestic academic exchanges. Among them, 4 articles are listed in ISTP and 13 articles are listed in EI.
Main Research Achievements (1) High Temperature Reactor Projects: The demonstration project of the High Temperature Gas-Cooled Reactor-Pebble-bed Module (HTR-PM) has gradually entered the stage of installation, commissioning, criticality and power generation, as well as commercial operation. Division 104 is the team responsible for the design of the main equipment, the first and second loops, as well as the main process system and the special safety system. They have made significant contributions to the commissioning, criticality and power up generation of HTR-PM. Significant progress has been made on HTR-PM600 projects, which open up a wide field for the commercial application of high temperature gas-cooled reactors. In the past five years, the division carried out the preliminary and construction design of HTR-PM600, and summarized the design items. The division has more than ten invention patents. (2) Low Temperature Reactor Projects: the Division provide technical supports to two low-temperature reactor projects. (3) High-Flux Reactor projects: the division has completed the following tasks: the 3D modelling design of the reactor, pressure vessel, and inner components; the component drawings of the pressure vessel and internal components of the reactor during the feasibility study stage; the feasibility study report of the pressure vessel, reactor internals, fuel handling and storage system; the design instructions for the pressure vessel, reactor internals, fuel handling and storage system; the preliminary seismic analysis of the pressure vessel and internal components of the reactor, including the seismic analysis of the pressure vessel in the pool; the preliminary internal flow distribution calculation; and the preliminary numerical simulation of the critical flow rate in the core area. The division also completed the project of "Intelligent Realization and Principle Prototype Development of High-Precision Irradiation Container Loading and Unloading Equipment" for the development of a remote-operated robotic arm for irradiation tanks in the reactor, which has passed project review.