HTGR Knowledge Base

Conference Article: Stress and Seismic Calculation of HTR-10 SG Accident Discharge System

J. Gong, J. Fu and S. Yu, Institute of Nuclear Energy Technology, Tsinghua University, China

Abstract

Steam Generator (SG) heat transfer tubes of 10MW High Temperature Gas Cooled Reactor (HTR- 10) are protective screens between the primary loop of helium and the secondary loop of water and steam. Water and steam will enter into the primary loop from the secondary loop if the SG heat transfer tubes rupture, which lead to increase of the primary loop pressure and discharge of radioactive materials.

Function of the SG accident discharge system (SGADS) is to discharge water and steam, so that the amount of water entering into the primary side could be reduced. The SGADS is connected with the main feedwater piping system. If the pipe ruptures, the coolant of the secondary loop will lose. This might cause unplanned reactor shut down. So it is important to guarantee the integrity of the SGADS. This paper presents stress and seismic calculation and analysis of the SGADS by use of PIPESTRESS. Results show that stress distributions satisfy the requirements of ASME codes for Classes 2 components.

view the full text of this article (5 pages, format: PDF, size= 180kB)


key words: Gas Cooled Reactor, Nuclear Technology
Reference:
Proceedings of the Conference on High Temperature Reactors, Petten, NL, April 22-24, 2002
Organized by HTR-TN in cooperation with the European Nucler Society (ENS) and the IAEA
International Atomic Energy Agency, Vienna (Austria)
HTR-2002, pp:1-5