@article{741e0d2159684f0f9b135a408b7cfb04,
title = "Feasibility Assessment of a Natural-Circulation Salt Irradiation Loop in the Advanced Test Reactor",
abstract = "Molten-salt reactors will likely require some level of irradiation testing as part of their licensing basis. An ideal experiment would consider the integrated effect of neutron flux and fission product generation in addition to circulating flow conditions. The feasibility of a natural-circulation irradiation salt loop in the Advanced Test Reactor (ATR) is assessed here. The flow is induced by the innovative combination of gas gaps and fin gaps along the capsule wall to fine-tune radial heat conductance, and therefore drive an axial temperature gradient across the experiment height. Following multiple design optimizations, a promising configuration has been identified. The 45-kW experiment would generate a 0.15 m/s flow velocity with 6 kg of fuel-bearing salt. This demonstrates the possibility of generating appreciable flow rates within manageable experimental conditions (e.g., total size and heat generation). An initial assessment of species mass tracking inside the experiment was also performed to gain an understanding of radionuclide behavior within the system. Results showed that significant quantities of Xe can be extracted in the off-gas (1.7 kCi) for an 8\% bubble removal efficiency rate. These results highlight the potential value of such experiments. Further work will involve detailed engineering drawings and analyses of the loop, as well as more computationally expensive modeling of species mass tracking.",
keywords = "Molten salt, irradiation loop, neutron transport, thermal hydraulics, species tracking",
author = "Abdalla Abou-Jaoude and Walker, \{Samuel A.\} and Sandesh Bhaskar and Wei Ji",
note = "Funding Information: The authors would like to thank Calvin Downey for assistance with generating CAD drawings and offering guidance on engineering considerations. Joe Palmer and Greg Core also provided valuable feedback on the experiment design and characteristics. The authors would also like to acknowledge the helpful discussions with Dr. Robert Salko Jr. from ORNL on species transport modeling capabilities in the CTF code and his support to allow access to CTF and the ORNL computing facilities. The research work was prepared for the U.S. Department of Energy (DOE) through the INL Laboratory Directed Research and Development program, grant number 20A1049-015FP, under the DOE Idaho Operations Office. It also made use of INL{\textquoteright}s high-performance computing resources (contract number DE-AC07-05ID14517). Last, the second author was also supported by a DOE Office of Nuclear Energy, Integrated University Program Graduate Fellowship. Funding Information: The authors would like to thank Calvin Downey for assistance with generating CAD drawings and offering guidance on engineering considerations. Joe Palmer and Greg Core also provided valuable feedback on the experiment design and characteristics. The authors would also like to acknowledge the helpful discussions with Dr. Robert Salko Jr. from ORNL on species transport modeling capabilities in the CTF code and his support to allow access to CTF and the ORNL computing facilities. The research work was prepared for the U.S. Department of Energy (DOE) through the INL Laboratory Directed Research and Development program, grant number 20A1049-015FP , under the DOE Idaho Operations Office. It also made use of INL{\textquoteright}s high-performance computing resources (contract number DE-AC07-05ID14517). Last, the second author was also supported by a DOE Office of Nuclear Energy, Integrated University Program Graduate Fellowship. Publisher Copyright: {\textcopyright} Copyright This work was authored as part of the Contributor{\textquoteright}s official duties as an Employee of the United States Government and is therefore a work of the United States Government. In accordance with 17 USC. 105, no copyright protection is available for such works under US Law.",
year = "2021",
month = dec,
day = "2",
doi = "10.1080/00295450.2020.1843954",
language = "English",
volume = "207",
pages = "1821--1841",
journal = "Nuclear Technology",
issn = "0029-5450",
publisher = "Taylor and Francis Ltd.",
number = "12",
}