شماره ركورد كنفرانس :
3254
عنوان مقاله :
Thermal-Hydraulics Investigation of the Helical Coil Steam Generator Tube Failure Accident in an Integral Pressurized Water Reactor
Author/Authors :
.A Fakhraeia Department of Nuclear Engineering - School of Mechanical Eng., Shiraz University 71936-51548 , .F Faghihia Safety Research Center - School of Mechanical Engineering, Shiraz , .M Amin Mozafarid Reactors and Accelerators Research and Development School - Nu clear Science and Technology Research Institute (NSTRI), Atomic Energy Organization of Iran , .M Nematollahia Safety Research Center - School of Mechanical Engineering, Shiraz , .A. S Noedoost Department of Nuclear Engineering - School of Mechanical Eng., Shiraz University 71936-51548
كليدواژه :
Passive Safety , Small Modular Reactor , Integral Pressurized Water Reactor
عنوان كنفرانس :
پنجمين كنفرلنس بين المللي قابليت اطمينان و ايمني
چكيده لاتين :
In this work, an integral pressurized water reactor modeled using RELAP5/SCDAP MOD 3.4 and steam generator tube failure accident is modeled. A steam generator tube failure (SGTF) could be caused by a rapid propagation of a crack that leads to a double-ended rupture of the tube. Reactor coolant goes across the primary side of the SG to the secondary side where steam is produced and travels through the main steam lines. It has the potential risk of radioactive material leakage to the environment. Due to the new design of steam generator and primary circuit in NuScale power module, it is observed that sequence of events is different from the current LWRs. Results from this work show that acceptance criteria are met in the situation of steam generator tube failure (SGTF) and core parameters will remain within safe limits.
