Super Critical Water Reactors GIF System Steering Committee
The Super Critical Water Reactors System Steering Committee (SCWR SSC) was formed following the signing of the SCWR System Arrangement in 2006. Currently, five members of the Generation IV International Forum (GIF) are engaged in the activities of the SCWR SSC. This committee supervises four projects encompassing a wide array of subjects pertaining to Super Critical Water Reactors. The SCWR is the only water cooled reactor among the six Generation IV systems and is a relatively evolutionary approach from current light water reactors (LWRs) that compose the majority of the reactors operated today, it also benefits from the experience of modern fossil fueled plants that rely on a energy conversion system using super-critical water.
Activities and Membership of the Super Critical Water Reactors GIF System Steering Committee
GIF SCWR SSC gathers five GIF Members. It oversees three R&D cooperation projects.
SCWR Projects
| Project Arrangement | Project Description | Effective Date | SIGNATORIES (GIF Member) | Chairs and co Chairs |
|---|---|---|---|---|
| SCWR materials and chemistry (M&C) |
| 2010 | NRCan (CA) | Chair: SÁEZ MADERUELO, Alberto (CIEMAT, Euratom) Co-Chair: Open |
| SCWR thermal-hydraulics and safety (TH&S) |
| 2009 | NRCan (CA) | Chair: ZHAO, Xuebin (NPIC, China) Co-Chair: NAVA-DOMINGUEZ, Armando (CNL, Canada) |
| Provisional SCWR system integration and assessment (SIA) |
| 2017 | NRCan (CA) |
If you want to learn more about the Super Critical Water Reactor technology head to the SCWR System description page. If you want to learn more about the latest outcomes and international efforts carried out under the GIF SCWR SSC please refer to the most recent GIF Annual Report.
SCWR SSC Leadership & Technical Secretariat
Dr
Armando NAVA-DOMINGUEZ
Armando Nava Dominguez has a Bachelor’s degree in Energy Engineering, specialized in Nuclear Thermalhydraulics and a Master’s degree in Nuclear Thermalhydraulics. He joined CNL in 2005 as a Thermalhydraulics Analyst, specializing in code development and validation of the subchannel code ASSERT-PV. He joined the Canadian Super Critical Water Reactor (SCWR) team in 2011 as part of the Generation-IV International Forum (GIF) program. He is the Canadian member and co-chair of the SCWR Thermalhydraulics and Safety under GIF. He is currently the chairman of the system steering committee for the SCWR under GIF. At CNL, he is the Technical and Project Lead of the SCWR Gen IV project, and Head of the Advanced Reactor Technologies section. In addition, he has five years of experience in the private sector conducting deterministic and probabilistic safety analyses of nuclear power plants.
Dr
Alberto SÁEZ MADERUELO
Alberto Sáez-Maderuelo has been working as a researcher at Centro de Investigaciones Energéticas Medioambientales y Tecnológicas (CIEMAT) since 2009, focusing his efforts on the study of corrosion behavior of structural materials for nuclear applications. Specifically, Alberto has studied the behavior of materials in simulated environments of Pressurized Water Reactor (PWR) and Supercritical Water Reactor (SCWR). In addition, Alberto is the leader of the project management board on materials and chemistry and the co-chair of the system steering committee of the SCWR-Generation IV International Forum (GIF). Alberto also serves as the leader of the materials work package in the European Union-funded project ECC-SMART, which studies the corrosion behavior of different candidate materials for the fabrication of cladding for the future supercritical water-cooled small modular reactor (SCW-SMR).
Dr
Elena POPLAVSKAIA
Elena Poplavskaia is a Nuclear Scientist in the division of the Nuclear Science and Education and Data Bank at the OECD/NEA. She also provides Technical Secretariat for the Generation IV International Forum (GIF) supporting the SCWR Steering Committee, SCWR Project Management Boards on Thermal-hydraulics and Safety, Materials and Chemistry, SCWR provisional Project Management Board on System Integration and Analysis, the VHTR Fuel and Fuel Cycle Project Management Board and the Advanced Manufacturing and Materials Engineering Working Group.
Prior joining the NEA in 2013 she was the head of a Research Centre laboratory, where she led the activities on system analysis of nuclear energy systems including advanced fast reactors and closed fuel cycle technologies, innovative institutional approaches to nuclear energy deployment and long-term aspects of achieving sustainability in the cycle. She was also involved in co-operation with the IAEA INPRO project. She holds a PhD in Engineering Science.