Water Cooled Reactors (WCRs) have been the cornerstone of the nuclear industry in the 20th century. As we move along in the 21st century and the nuclear community worldwide looks into the future with the development of advanced and innovative reactor designs and fuel cycles, it is clear that WCRs will continue to play an important role in this future. Although it is possible to learn a lot from the many reactor-years of experience and know-how accumulated by the safe operation of WCRs worldwide, this is still a young technology and there are numerous opportunities for innovation and to expand the use of WCRs beyond the current applications. Furthermore, it is also expected that WCRs will become a bridge towards promising future nuclear technologies that are not quite commercially feasible just yet, such as FRs.
This project serves as the IAEA center of excellence on technology advances for achieving competitive economics and reliability in future Water Cooled Reactors, while meeting stringent safety requirements. Member States and the IAEA rely on this project to obtain accurate, current and balanced information about the latest developments in water cooled reactor technology worldwide. The project also fosters and coordinates technology advances by facilitating collaborative research and development in key areas of common interest. It also provides state of the art technology training materials for the next generation of nuclear professionals.
Areas of interest for international collaboration are identified by Member States through participation in the IAEA Nuclear Energy Department's Technical Working Groups on Advanced Technologies for LWRs and HWRs (the TWG-LWR and the TWG-HWR). The TWG-LWR and TWG-HWR are groups of experts that provide advice and support for programme implementation, reflecting a global network of excellence and expertise in the area of advanced technologies for Water Cooled Reactors.
| Date | Meeting | Location | Responsible Officer |
|---|---|---|---|
| 27-30 Mar | Third Workshop of ICSP on Integral PWR Design Natural Circulation Flow Stability and Thermo-hydraulic Coupling of Containment and Primary System during Accidents | Daejeon, Korea | J.H. Choi |
| 5-7 Jun | Technical Meetings of TWG-LWR and TWG-HWR | IAEA, Vienna | J.H. Choi, M. Harper |
| 23-27 Jul | Training Course on Natural Circulation Phenomena and Passive Safety Systems in Advanced Water Cooled Reactors | Oregon State University, USA | J.H. Choi |
| Date | Meeting | Location | Responsible Officer |
|---|---|---|---|
| 21-23 Mar | 2nd Workshop for ICSP on "Integral PWR Design Natural Circulation Flow Stability and Thermo-hydraulic Coupling of Containment and Primary System during Accidents" | IAEA, Vienna | J.H. Choi |
| 12-14 Apr | 2nd Workshop on "Good Practices in Heavy Water Reactor Operation" |
Gyeongju,
Korea |
J.H. Choi |
|
27 Jun
1 Jul |
Joint ICTP-IAEA Course on Science and Technology of Supercritical Water Cooled Reactors | Trieste, Italy | J.H. Choi |
| 11-15 Jul | Training Course on Natural Circulation Phenomena and Passive Safety Systems in Advanced Water Cooled Reactors |
Harbin,
P.R. China |
J.H. Choi |
| 26-28 Jul | 16th Meeting of TWG-LWR and 12th Meeting of TWG-HWR | IAEA, Vienna | J.H. Choi |
|
30 Aug
2 Sep |
3rd RCM of CRP on Benchmarking Severe Accident Computer Codes for HWR Applications |
Daejeon,
Rep. of Korea |
J.H. Choi |
| 16-18 Nov | Workshop on the Prediction of Axial and Radial Creep in HWR Pressure Tubes | IAEA, Vienna | J.H. Choi |
| 12-14 Dec | TM on Fuel Design and Licensing of Mixed Cores for Water Cooled Reactors | IAEA, Vienna | J.H. Choi |
| Date | Meeting | Location | Responsible Officer |
|---|---|---|---|
| 16-19 Mar | Workshop of ICSP on Integral PWR Design Natural Circulation Flow Stability and Thermo-Hydraulic Coupling of Containment and Primary System during Accidents | Corvallis, Oregon, USA | J.H. Choi |
| 04-07 May | TM on Benchmarking Severe Accident Computer Codes for Heavy Water Reactor Applications | Mumbai, India | J.H. Choi |
| 10-14 May | TC Workshop: Project Management for New Nuclear Power Projects |
Ulsan, Rep. of Korea |
K.-S. Kang, S. Bilbao |
| 17-21 May | Training Course on Natural Circulation Phenomena and Passive Safety Systems in Advanced Water Cooled Reactors | Trieste, Italy | J.H. Choi |
|
27 Jun - 1 Jul |
Joint Meeting of the Technical Working Group on Advanced Technologies for LWR and HWR | IAEA, Vienna |
S. Bilbao, J.H. Choi |
| 14-16 Dec | TM on Application of CFD Codes for the Design of Advanced Water Cooled Reactors | IAEA, Vienna | S. Bilbao |
| Date | Meeting | Responsible Officer |
|---|---|---|
| 22-26 Jun | Course on Natural Circulation Phenomena and Modeling in Water Cooled Nuclear Power Plants | J.H. Choi |
| 12-23 Oct | Workshop on Nuclear Power Plant (NPP) Simulators for Education | S. Bilbao |
| 27-30 Oct | International Conference on Opportunities and Challenges for Water Cooled Reactors in the 21st Century | S. Bilbao |
| 23-26 Nov | TM on Advanced Fuel Pellet Materials and fuel Rod Designs for Water Cooled Reactors |
S. Bilbao, V. Inozemtsev |
CRP on Benchmarking Severe Accident Computer Codes for Heavy Water Reactor Applications
CRP on Intercomparison of Techniques for Inspection and Diagnostics of HWR Pressure Tubes
ICSP on "Simulation Results for Small Break LOCA (SBLOCA) Accidents on HWRs"
ICSP on Integral PWR Design Natural Circulation Flow Stability and Thermo-hydraulic Coupling of Containment and Primary System during Accidents
NE Series on Best Practices for HWR operational excellence
Construction Technologies for New Nuclear Plants
NE Series on Role of HWR for efficient use of fissionable resources
Use of CFD Codes for Modelling, Simulation and Design of Advanced Water Cooled Reactors
Use of Thorium in existing and future HWRs & LWRs
Advanced Reactor Physics for HWRs
ARIS
Advanced Fuel Pellet Materials and Fuel Rod Design for Water Cooled Reactors
IAEA-TECDOC-1654 (December 2010)
Good Practices in Heavy Water Reactor Operation
IAEA-TECDOC-1650 (June 2010)
Passive Safety Systems in Water Cooled Nuclear Power Plants: Natural Circulation: Natural Circulation
IAEA-TECDOC-1624 (November 2009)
Intercomparison of Techniques for Inspection and Diagnostics of Heavy Water Reactor Pressure Tubes: Determination of Hydrogen Concentration and Blister Characterization: Determination of Hydrogen Concentration and Blister Characterization
IAEA-TECDOC-1609 (March 2009)
Advanced Applications of Water Cooled Nuclear Power Plants
IAEA-TECDOC-1584 (July 2008)