TY - GEN
T1 - Review of Neutronics, Thermal-Hydraulic, and Fuel Performance Research of Accident Tolerant Fuels for APR-1400 in United Arab Emirates Nuclear Power Plants
AU - Alzarooni, Asma
AU - Alrwashdeh, Mohammad
AU - Chaudri, Khurrum Saleem
AU - Alameri, Saeed A.
N1 - Publisher Copyright:
© The Author(s), under exclusive license to Springer Nature Switzerland AG 2024.
PY - 2024
Y1 - 2024
N2 - The UAE’s nuclear energy program, which began in 2008 with the publication of the “UAE Policy on the Peaceful Use of Nuclear Energy” document, has prioritized the safe, reliable, and economic operation of its APR-1400 nuclear power plants at Barakah. Following the Fukushima accident, the development of Accident Tolerant Fuels (ATFs) has become a focus in the nuclear fuel research and development community. ATFs are designed to withstand a significant loss of active cooling in the reactor core for a longer period, resulting in increased safety compared to the existing fuel system while maintaining or improving normal operation performance. The purpose of this study is to investigate the feasibility of using ATFs as nuclear fuel in the APR-1400 nuclear power plants (BNPPs) and assess their impact on the plant’s safety and operation parameters. To accomplish this goal, a variety of analyses and assessments will be necessary, including neutronics, thermal-hydraulic, thermo-mechanical/chemical, and fuel performance analyses for multiple candidate ATF concepts. The investigation will focus on the APR-1400 reactor, which is the reactor of choice in Barakah plants. The study aims to provide a review of ongoing research and potential ATF concepts for use in the near future in APR-1400 nuclear power plants.
AB - The UAE’s nuclear energy program, which began in 2008 with the publication of the “UAE Policy on the Peaceful Use of Nuclear Energy” document, has prioritized the safe, reliable, and economic operation of its APR-1400 nuclear power plants at Barakah. Following the Fukushima accident, the development of Accident Tolerant Fuels (ATFs) has become a focus in the nuclear fuel research and development community. ATFs are designed to withstand a significant loss of active cooling in the reactor core for a longer period, resulting in increased safety compared to the existing fuel system while maintaining or improving normal operation performance. The purpose of this study is to investigate the feasibility of using ATFs as nuclear fuel in the APR-1400 nuclear power plants (BNPPs) and assess their impact on the plant’s safety and operation parameters. To accomplish this goal, a variety of analyses and assessments will be necessary, including neutronics, thermal-hydraulic, thermo-mechanical/chemical, and fuel performance analyses for multiple candidate ATF concepts. The investigation will focus on the APR-1400 reactor, which is the reactor of choice in Barakah plants. The study aims to provide a review of ongoing research and potential ATF concepts for use in the near future in APR-1400 nuclear power plants.
KW - Accident Tolerant Fuel
KW - Neutronics
KW - Thermal hydraulics
KW - Thermomechanical
UR - https://www.scopus.com/pages/publications/85200783024
U2 - 10.1007/978-3-031-64362-0_25
DO - 10.1007/978-3-031-64362-0_25
M3 - Conference contribution
AN - SCOPUS:85200783024
SN - 9783031643613
T3 - Lecture Notes in Mechanical Engineering
SP - 248
EP - 259
BT - Challenges and Recent Advancements in Nuclear Energy Systems - Proceedings of Saudi International Conference on Nuclear Power Engineering SCOPE
A2 - Shams, Afaque
A2 - Al-Athel, Khaled
A2 - Tiselj, Iztok
A2 - Pautz, Andreas
A2 - Kwiatkowski, Tomasz
PB - Springer Science and Business Media Deutschland GmbH
T2 - Saudi International Conference on Nuclear Power Engineering, SCOPE 2023
Y2 - 13 November 2023 through 15 November 2023
ER -