Review of Neutron Physics Analyses for Accident-Tolerant Fuel System

Khurrum Saleem Chaudri1,2

Mohammad Alrwashdeh1,2

Ho Jin Ryu3

Saeed A. Alameri1,2,Email

1Department of Mechanical and Nuclear Engineering, Khalifa University of Science and Technology, Abu Dhabi P.O. Box 127788, United Arab Emirates.
2Emirates Nuclear Technology Center (ENTC), Khalifa University of Science and Technology, P.O. Box 127788, Abu Dhabi, United Arab Emirates.
3Department of Nuclear and Quantum Engineering, Korea Advanced Institute of Science and Technology (KAIST), 291 Daehak-ro, Yuseong-gu, Daejeon, 34141, Republic of Korea.


After the 2011 Fukushima nuclear accident, scientists and engineers have been developing accident-tolerant fuel (ATF) concepts to make nuclear reactors safer. To make light-water reactor fuel-cladding systems more resistant to accidents, researchers are proposing solutions to the problem of Zr-based cladding oxidation. Researchers are proposing to improve the accident tolerance of current fuel cladding systems by enhancing Zr-based alloys or coating Zircaloy, or by using new cladding/fuel materials. Neutron physics is essential for evaluating the feasibility of these solutions. It will be used to assess not only their safety but also their economic viability. This review summarises the nuclear industry's efforts to investigate the reactor physics impact of accident-tolerant fuel (ATF) concepts on current and future reactor designs. Important reactor physics parameters that affect safety and economics include reactivity coefficients, cycle length, neutron spectrum, excess reactivity, and control rod worth. This work can serve as a reference for the nuclear community, especially reactor physicists when studying ATF concept implementation.

Review of Neutron Physics Analyses for Accident-Tolerant Fuel System