TY - GEN
T1 - Deployment and In-reactor Test of an Instrument for Real-time Monitoring Thermal Conductivity Evolution of Nuclear Fuels
AU - Hua, Zilong
AU - Picklesimer, Caleb
AU - Fleming, Austin
AU - Hurley, David
AU - Zhou, Weiyue
AU - Short, Michael
AU - Carpenter, David
N1 - Funding Information:
This work is supported by D epartment of Energy – Nuclear Energy, Consolidated Innovative Nuclear Research (CINR) under contract number NFUS -21-24335. The authors would like to acknowledge and thank the staff at Massachusetts Institute of Technology Research Reactor, rD s. Michael Ames, aY kov Ostrovsky, oG rdon Kohse, and Mike oG rdon, for the technical advice and support. The authors would also thank the Idaho National Laboratory machine shop and Advanced Manufacturing group, specifically, Drs . Jorgen Rufner, Arin Preston, and Richard Hatch, for fabricating the instrument parts and samples.
Funding Information:
This work is supported by Department of Energy – Nuclear Energy, Consolidated Innovative Nuclear Research (CINR) under contract number NSUF-21-24335. The authors would like to acknowledge and thank the staff at Massachusetts Institute of Technology Research Reactor, Drs. Michael Ames, Yakov Ostrovsky, Gordon Kohse, and Mike Gordon, for the technical advice and support. The authors would also thank the Idaho National Laboratory machine shop and Advanced Manufacturing group, specifically, Drs. Jorgen Rufner, Arin Preston, and Richard Hatch, for fabricating the instrument parts and samples.
Publisher Copyright:
© 2023 American Nuclear Society, Incorporated.
PY - 2023
Y1 - 2023
N2 - Thermal conductivity of nuclear fuels directly ties to the reactor safety and efficiency. Because of the microstructure defects generated and evolved in the extreme in-reactor environment, thermal conductivity of nuclear fuels reduces significantly during the reactor operation. A better understanding of the scattering mechanisms between defects and thermal carriers could explain and predict the fuel performances in reactor. Currently, the efforts primarily rely on the post-irradiation-examination (PIE). However, a primary type of phonon scatters, point defects, anneal at high temperature after the reactor shutdown and before PIE can be performed. We developed a photothermal radiometry (PTR) based instrument to fill this technical gap. Here we reported its development and deployment to Massachusetts Institute of Technology Research Reactor (MITR). The instrument design was adapted according to the geometry requirements of MITR and the results of thermal and neutronic analyses. Four fiber probes were included in the instrument to enable multiple measurements at the same time, with three preloading reference materials and one testing the fiber survivability. The final temperature of the materials was lower than expected, likely due to the oversimplification of the thermal analysis model. Real-time thermal diffusivity of Al2O3 was successfully measured with neutron irradiation in the temperature range of 400–440°C. The causes of difference between measurement results and literature values are discussed.
AB - Thermal conductivity of nuclear fuels directly ties to the reactor safety and efficiency. Because of the microstructure defects generated and evolved in the extreme in-reactor environment, thermal conductivity of nuclear fuels reduces significantly during the reactor operation. A better understanding of the scattering mechanisms between defects and thermal carriers could explain and predict the fuel performances in reactor. Currently, the efforts primarily rely on the post-irradiation-examination (PIE). However, a primary type of phonon scatters, point defects, anneal at high temperature after the reactor shutdown and before PIE can be performed. We developed a photothermal radiometry (PTR) based instrument to fill this technical gap. Here we reported its development and deployment to Massachusetts Institute of Technology Research Reactor (MITR). The instrument design was adapted according to the geometry requirements of MITR and the results of thermal and neutronic analyses. Four fiber probes were included in the instrument to enable multiple measurements at the same time, with three preloading reference materials and one testing the fiber survivability. The final temperature of the materials was lower than expected, likely due to the oversimplification of the thermal analysis model. Real-time thermal diffusivity of Al2O3 was successfully measured with neutron irradiation in the temperature range of 400–440°C. The causes of difference between measurement results and literature values are discussed.
KW - In-reactor thermal transport measurement
UR - https://www.scopus.com/pages/publications/85183315436
U2 - 10.13182/NPICHMIT23-41033
DO - 10.13182/NPICHMIT23-41033
M3 - Conference contribution
AN - SCOPUS:85183315436
T3 - Proceedings of 13th Nuclear Plant Instrumentation, Control and Human-Machine Interface Technologies, NPIC and HMIT 2023
SP - 1298
EP - 1303
BT - Proceedings of 13th Nuclear Plant Instrumentation, Control and Human-Machine Interface Technologies, NPIC and HMIT 2023
PB - American Nuclear Society
T2 - 13th Nuclear Plant Instrumentation, Control and Human-Machine Interface Technologies, NPIC and HMIT 2023
Y2 - 15 July 2023 through 20 July 2023
ER -