Very High Temperature Reactors GIF System Steering Committee
The Very High Temperature Reactor System Steering Committee (VHTR SSC) was established after the VHTR System Arrangement was signed in 2006. Presently, nine members of the Generation IV International Forum (GIF) participate in the VHTR SSC's activities. This committee oversees four projects that cover a broad range of topics related to Very High Temperature Reactors. The VHTR, along with Sodium Fast Reactors, is one of the Generation IV systems that has commercial-scale power reactors in operation today and has also had several in operation previously.
Activities and Membership of the Very High Temperature Reactors GIF System Steering Committee
GIF VHTR SSC gathers ten GIF Members. It oversees four R&D cooperation projects.
VHTR Projects
| Project Arrangement | Project Description | Effective Date | SIGNATORIES
(GIF Member) |
|---|---|---|---|
| Fuel and Fuel Cycle (FFC) | The Fuel and Fuel Cycle project focuses on developing solutions for VHTR fuel, specifically TRISO-coated particles. The project explores potential fuel development such as uranium oxycarbide kernels or ZrC coatings to improve burnup capability, reduce fission product release, and increase resistance to core heat-up accidents. | 2008 | JRC (EU) |
| Computational Methods, Validation & Benchmarks (CMVB) | Validation of new computational methods and codes in the areas of HTR thermal-hydraulics, thermal mechanics, core physics and chemical transport are needed for the design and licensing assessment of reactor performance in accident conditions. | 2013 | INET (CN) |
| Hydrogen Production (HP) | Recent Project focus has been on the hybrid copper-chlorine thermo-chemical and the hybrid sulfur cycles. R&D efforts in this PMB address material development, feasibility, optimization, efficiency and economic evaluation for industrial-scale hydrogen production. Performance and optimization of hydrogen production processes are being assessed through integrated test loops, from laboratory | 2008 | NRCan (CA) |
| Material (MAT) | VHTR-MAT PMB mainly focuses on advanced materials development, additional materials’ testing standard and code development, and develops and maintains the “GenIV materials handbook”. The Gen IV Materials Handbook, initially developed for the US Gen IV Nuclear Energy Systems Program, became the shared international database it is today starting from April 2007. The handbook evolved into a sophisticated materials information management system with secured access control, data processing tools, and a flexible framework for enhancement, aiming to satisfy the research needs of international Gen IV nuclear reactor programs. | 2009 | NRCan (CA) - joined in 2024 |
If you want to learn more about the Very High Temperature Reactor technology head to the VHTR System description page. If you want to learn more about the latest outcomes and international efforts carried out under the GIF VHTR SSC please refer to the most recent GIF Annual Report.