Invited Plenary Session Speakers
“Global Overview of the Energy Scene”, Dr Andrew Minchener (IEACCC), UK
“Experiences on the materials service in the Chinese Ultra Super Critical power plant”, Prof Liu Zhengdong (CISRI), CN
“Five Decades of High Temperature Design”, Prof James Boyle (University of Strathclyde), UK
“Update on United States Advanced Ultra-supercritical Component Test Project for 760°C Steam Conditions”, Dr Robert Purgert (Energy Industries of Ohio), USA & Mr Horst Hack (EPRI), USA
Following the successful completion of a 15-year effort to develop and test materials that would allow advanced ultra-supercritical (A-USC) coal-fired power plants to be operated at steam temperatures up to 760°C, a United States-based consortium has been working on a project (A-USC ComTest) to help achieve technical readiness to allow the construction of a commercial scale A-USC demonstration power plant. Among the goals of the ComTest project are to validate that components made from the advanced alloys can be designed and fabricated to perform under A-USC conditions, to accelerate the development of a U.S.-based supply chain for key A-USC components, and to decrease the uncertainty for cost estimates of future commercial-scale A-USC power plants. This project is intended to bring A-USC technology to the commercial scale demonstration level of readiness by completing the manufacturing R&D of A-USC components by fabricating commercial scale nickel-based alloy components and sub-assemblies that would be needed in a coal fired power plant of approximately 800 megawatts (MWe) generation capacity operating at a steam temperature of 760°C (1400°F) and steam pressure of at least 238 bar (3500 psia).
The A-USC ComTest project scope includes fabrication of full-scale superheater / reheater components and subassemblies (including tubes and headers), furnace membrane walls, steam turbine forged rotor, steam turbine nozzle carrier casting, and high temperature steam transfer piping. Materials of construction include Inconel 740H and Haynes 282 alloys for the high temperature sections. The project team will also conduct testing and seek to obtain ASME Code Stamp approval for nickel-based alloy pressure relief valve designs that would be used in A-USC power plants up to approximately 800 MWe size.
The U.S. consortium, principally funded by the U.S. Department of Energy and the Ohio Coal Development Office under a prime contract with the Energy Industries of Ohio, with co-funding from the power industry participants, General Electric, and the Electric Power Research Institute, has completed the detailed engineering phase of the A-USC ComTest project, and is currently engaged in the procurement and fabrication phase of the work.
This paper will outline the motivation for the effort, summarize work completed to date, and detail work scope for the remainder of the A-USC ComTest project.
“High temperature material requirements for the design of next generation nuclear power plants”, Dr Hyeong-Yeon Lee (KAERI), KR
Thermal efficiency of the currently deployed fleet of Generation III+ nuclear power plants with water-cooled reactors cannot be increased significantly without completely different innovative designs, which are Generation IV reactors with at a high level of fuel efficiency, safety, proliferation-resistance, sustainability and cost. The high performance and reliability of materials when subjected to the higher temperature and neutron dose environments are material requirements in Gen IV nuclear reactors. In this study, reviews on materials, requirements and challenges for structural Gen IV material are made associated with design of Gen IV nuclear reactors that operate at high temperature in creep range. The requirements of nuclear-grade heat-resistant materials registered in high-temperature design codes of ASME Section III Division 5 and RCC-MRx are reviewed along with comparison of the two design codes with more focus on damage of creep and creep-fatigue. High-temperature design evaluation platform of ‘HITEP’ was developed by KAERI which enables a designer to perform high-temperature design in reliable and efficient way according to the two design codes. Development status of the Gen IV structural materials along with technical challenges in high and very high-temperature for specific Gen IV reactors are discussed.
Generally the keynote speaker will be selected from abstracts presented to a session.