Advanced Fuel Development
The development of Robust or Accident Tolerant Fuel (ATF) has become an international area of interest and effort in the last few years. Conceptually ATF would provide leap-ahead improvement in Light Water Reactor (LWR) fuel safety during beyond design basis accidents and commercial benefit to nuclear utilities. Accelerated by the severe accident at the Fukushima Daiichi nuclear power plant in Japan, a variety of research, development and commercial analysis of ATF is presently underway globally. The insertion of ATF lead test rods (LTR) into a commercial PWR has been underway since 2019.
This panel will present and discuss the state-of-art knowledge of ATF from the point of view of industry, government, non-profit research agencies, and academic representatives currently leading global ATF development. The significant challenges in development and implementation of ATF, such as large scale ATF fabrication, acceptance by nuclear utilities, the role of government and inter-government agencies in ATF research oversight, and the engineering and scientific challenges to develop ATF will be presented. The goal of this panel is to communicate the current understanding of the commercial and technical challenges faced in ATF development.
Westinghouse Advanced Manufacturing Technologies for Nuclear Applications
Advanced Electron Beam Welding Technology for Manufacturing Nuclear Power Plant Components
A Novel Technology of Manufacturing Pressure Vessels Used in PWRs
Micro & Small Modular Reactors/Advanced Nuclear System
The micro reactors, small modular reactors and advanced reactors have the potential to reduce greenhouse gas emissions by displacing fossil fuels in the generation of electricity and in the application of process heat for number of energy intensive industrial products.
These reactors are characterized by high energy density, less nuclear waste and offer simplified operation and maintenance for multiple application scenarios, such as for distributed power and load-following applications, meanwhile increased security, economy and proliferation resistance. Particularly, the Generation IV reactors represent the development trend of advanced reactors, among which lead fast reactors (LFR) is expected as the first to realize industrialization.
This panel will discuss about technology development progress and status on advanced reactors, micro reactors and small modular reactors.
Space and Other Applications of Nuclear Energy
Besides the applications of energy for the civil electricity production in power plants the technology has essential uses across multiple sectors, including consumer products, food and agriculture, industry, medicine and scientific research, transport, and water resources and the environment. For space application Radioisotope Thermoelectric Generators (RTGs) have been used since 1960s, and recently fission micro reactors are considered for mars and deep space missions. The panel will discuss some of recent developments and advances in the application of nuclear energy in space missions, medical diagnostics and therapy, plant mutation and breeding, food irradiation, sterilization, pest control non-destructive diagnostics, instrumentation, nuclear power ships, propulsion, and as tracers.
AP1000 Plant Experience
AP1000, one of the advanced reactors, is featured for its passive technology, high safety, and simplified system configuration and manipulation. Four AP1000 units have been in safe and reliable operation for over 2 years in China. The AP1000 plants have also achieved high performance, operational economy and record refueling outage duration on account of both advanced technology and good operational management. With its safety, economy and load-following capacity, AP1000 plants can play a more important role in carbon reduction. This panel will discuss magnificent experiences and production management optimization efforts of AP1000 plants to facilitate its application,and will cover all phases such as engineering，commissioning，operation，outage，and so on.
Severe Accidents - Mitigation, Planning, Management
The nuclear safety is always a big concern in nuclear industry, in particular after Fukushima Daiichi accident. Efforts have been made to prevent and mitigate the likelihood and impact of the severe accident in Gen III reactor design, such as IVR & EVR strategies adopted in various designs, as well as management of hydrogen risk, source term containment. This panel will present and discuss the recent progress of R&D in corium retention, code development, among others, facing the challenges in next generation reactor design.
Fukushima Panel - 10 years Later
This Panel Session will be chaired by Dr Tadashi Narabayashi, he was an advisory meeting member of NISA with regard to technical lessons learned from the Fukushima Daiichi NPP accidents, and he was the member of Fukushima Daiichi Accident Investigation Team in NRA (Nuclear Regulatory Authority). He is the chairman of the new committee to learn Black out of Hokkaido earthquake, a lot of Typhoons and heavy rain in PESD/JSME. The session will show the progress of decommissioning of the Fukushima Daiichi NPS, technology development, research projects for that purpose, and support for Fukushima reconstruction activities, such as cut off the stack, spent fuel removal and robotics technology.
Climate Change and Emission Reduction
This workshop will present an overview of some of the key Thermal-Hydraulic methodologies, experimentation procedure and its application to nuclear power plants. The relevant computer code model and theory will be described, and real experimental work will be presented and discussed. The workshop will feature both industry and academic experts who will present advances in thermalhydraulics methods, experiments, and simulations of key phenomena for safety assessment of various reactor systems and components. For exchanging information and experience purposes, this workshop is applicable to both students/professors and engineers in the relevant industry fields.
- Introduction and Overview of the TH Workshop
- Scaling For Thermal-hydraulics Experiments
- Fundamental Experiments and CFD Application for Large Advanced PWRs Development
- Fluid Transients in Piping Systems
- Thermal hydraulics aspects of leakage through cracked thin wall tubes
- PWR Safety Analysis Philosophy, WALT DNB/ATF Test Methodology, CIPS Phenomena and Analysis
Computational Fluid Dynamics
The CFD seminar will target young researchers, engineers, and students to provide the basis and results for a selection of several CFD applications for certain thermal-hydraulic problems. Wide variety knowledge and up-to-date information on CFD will be presented by leading CFD specialists. The presentations begin with the fundamental equations and numerical solution methods, and then continue to recent developments and some practical guidelines of CFD for nuclear engineering applications. Informal discussions and questions will be conducted.
Nuclear Codes and Standards
This workshop will promulgate an open technical exchange of information and sharing of lessons learned in response to current codes and standards needs. All interested stakeholders will contribute toward the development and modification of codes, standards, and conformity assessment activities and help identify international collaboration efforts.