TY - JOUR
T1 - Accident event progression, gaps, and key performance indicators for steam generator tube rupture events in water-cooled SMRs
T2 - A review
AU - Abdellatif, Hossam H.
AU - Bhowmik, Palash K.
AU - Arcilesi, David
AU - Sabharwall, Piyush
N1 - Funding Information:
The authors would like to thank the U.S. Department of Energy ( DOE ) Advanced Reactor Demonstration Project (ARDP) program office and the Irradiation Experiment and Thermal Hydraulics Analysis Department at Idaho National Laboratory ( INL ) for their encouragement and support.
Publisher Copyright:
© 2023
PY - 2024/3/1
Y1 - 2024/3/1
N2 - According to historical records of reactor-related incidents, a steam generator tube rupture (SGTR) is one of the most common occurrences at operating pressurized water reactors (PWRs). Such design-basis accidents (DBAs) could lead to a direct path for radionuclides to be released to the atmosphere via the safety and relief valves, making assessments of radionuclide discharge from operating nuclear power plants (NPPs) into the environment crucial for ensuring safety. In such analyses, the primary focus has been on the extent of radioactive release, not the potential damage to the core. Moreover, significant and timely intervention by operators is needed during the initial stages of SGTRs in order to avert overfilling of the SGs, as well as to restrict the dissemination of radioactive materials. Determining the event sequence and phases that occur during an SGTR incident in an advanced passive (e.g., AP1000) water-cooled nuclear reactor is crucial for implementing effective passive safety systems (PSSs) for a specific water-cooled small modular reactor (SMR) design. This study provides a comprehensive review of the accident event progression, associated physical phenomena, knowledge gaps, and key performance indicators that must be evaluated and assessed in thermal-hydraulics models, based on relevant test data, respectively.
AB - According to historical records of reactor-related incidents, a steam generator tube rupture (SGTR) is one of the most common occurrences at operating pressurized water reactors (PWRs). Such design-basis accidents (DBAs) could lead to a direct path for radionuclides to be released to the atmosphere via the safety and relief valves, making assessments of radionuclide discharge from operating nuclear power plants (NPPs) into the environment crucial for ensuring safety. In such analyses, the primary focus has been on the extent of radioactive release, not the potential damage to the core. Moreover, significant and timely intervention by operators is needed during the initial stages of SGTRs in order to avert overfilling of the SGs, as well as to restrict the dissemination of radioactive materials. Determining the event sequence and phases that occur during an SGTR incident in an advanced passive (e.g., AP1000) water-cooled nuclear reactor is crucial for implementing effective passive safety systems (PSSs) for a specific water-cooled small modular reactor (SMR) design. This study provides a comprehensive review of the accident event progression, associated physical phenomena, knowledge gaps, and key performance indicators that must be evaluated and assessed in thermal-hydraulics models, based on relevant test data, respectively.
KW - Accident management
KW - Advanced passive reactor
KW - AP1000
KW - SG
KW - SGTR
KW - SMR
KW - Thermal-hydraulics
UR - http://www.scopus.com/inward/record.url?scp=85181159057&partnerID=8YFLogxK
UR - https://www.mendeley.com/catalogue/e288b739-ffe8-3533-a4ec-35f58098327f/
U2 - 10.1016/j.pnucene.2023.105021
DO - 10.1016/j.pnucene.2023.105021
M3 - Review article
AN - SCOPUS:85181159057
SN - 0149-1970
VL - 168
SP - 105021
JO - Progress in Nuclear Energy
JF - Progress in Nuclear Energy
M1 - 105021
ER -