After a supposed accident lead the reactor to shutdown, the residual heat generated from the decay will be removed out by the cooling system. A cooling water flow will be pumped into the steam generator for cooling the reactor after the pressure of the secondary side of the steam generator is decreased to a lower design value with opening of the pressure relief valve which is installed on the live-steam pipeline. But the temperature of the heat-exchange tubes and the tube plate at the outlet of the steam generator whose temperature in the steady-state operation is 570° high, need to be cooled down to about 200° for the material limitation before the cooling water is injected, to avoid the cold-shock damage on the components. In this paper, exampled as the 200MWe high temperature gas cooled reactor (HTR-PM), a general thermal-hydraulic system analysis code is used for modeling and simulating numerically the pressure relief transient after the accident. The results show the structure components of the steam generator will be cooled down effectively to mitigate the cold-shock damage from the cooling water during the transient with the designed pressure value of 1MPa where the pressure relief valve in 30mm diameter will be closed. It provides supports for the evaluation on the feasibility of cooling water injection and also for the material stress analysis on some relevant components in the steam generator design.
Skip Nav Destination
2012 20th International Conference on Nuclear Engineering and the ASME 2012 Power Conference
July 30–August 3, 2012
Anaheim, California, USA
Conference Sponsors:
- Nuclear Engineering Division
- Power Division
ISBN:
978-0-7918-4496-0
PROCEEDINGS PAPER
Study on Pressure Relief Transient for High Temperature Gas Cooled Reactor
Yan Wang
Yan Wang
Tsinghua University, Beijing, China
Search for other works by this author on:
Yan Wang
Tsinghua University, Beijing, China
Paper No:
ICONE20-POWER2012-54124, pp. 269-274; 6 pages
Published Online:
October 30, 2013
Citation
Wang, Y. "Study on Pressure Relief Transient for High Temperature Gas Cooled Reactor." Proceedings of the 2012 20th International Conference on Nuclear Engineering and the ASME 2012 Power Conference. Volume 2: Plant Systems, Structures, and Components; Safety and Security; Next Generation Systems; Heat Exchangers and Cooling Systems. Anaheim, California, USA. July 30–August 3, 2012. pp. 269-274. ASME. https://doi.org/10.1115/ICONE20-POWER2012-54124
Download citation file:
8
Views
0
Citations
Related Proceedings Papers
Related Articles
Heat Exchanger Design Considerations for Gas Turbine HTGR Power Plant
J. Eng. Power (April,1977)
Ways to Increase Efficiency of the High-Temperature Gas Reactor Coupled With the Gas-Turbine Power Conversion Unit
J. Eng. Gas Turbines Power (September,2009)
Conceptual Structure Design of High Temperature Isolation Valve for High Temperature Gas Cooled Reactor
J. Eng. Gas Turbines Power (November,2011)
Related Chapters
Control and Operational Performance
Closed-Cycle Gas Turbines: Operating Experience and Future Potential
Thermal Interface Resistance
Thermal Management of Microelectronic Equipment, Second Edition
Introduction
Consensus on Operating Practices for Control of Water and Steam Chemistry in Combined Cycle and Cogeneration