TY - JOUR
T1 - Experimental burn-up analysis of ITU Triga Mark II reactor fuel elements
AU - Akyurek, Tayfun
AU - Reyhancan, Iskender Atilla
AU - Kiziltas, Muhammet Sahip
AU - Acikgoz, Dogukan
N1 - Publisher Copyright:
© 2024 Elsevier B.V.
PY - 2024/8
Y1 - 2024/8
N2 - In this study, burn-up values of spent fuels were determined using Non-Destructive Analysis (NDA) with the help of 137Cs burn-up indicator. Four spent fuel elements (F30, D18, B5 and E14) that burned in the core of the Istanbul Technical University Triga Mark II research reactor over the years were investigated with two different methods. In addition, the individual activity of the fuel elements along the axial fuel length was determined by the High Purity Germanium (HPGe) detector. As expected, it was determined that the fuel element B5, located in the center of the reactor core, exhibited the highest burn-up value with both methods. The calculations conducted using method 1 revealed a burn-up rate of 205.59 MWd/tHM for the B5 fuel element, while method 2 yielded a burn-up value of 5.40%. Experimental results were compared with previous simulation burn-up studies.
AB - In this study, burn-up values of spent fuels were determined using Non-Destructive Analysis (NDA) with the help of 137Cs burn-up indicator. Four spent fuel elements (F30, D18, B5 and E14) that burned in the core of the Istanbul Technical University Triga Mark II research reactor over the years were investigated with two different methods. In addition, the individual activity of the fuel elements along the axial fuel length was determined by the High Purity Germanium (HPGe) detector. As expected, it was determined that the fuel element B5, located in the center of the reactor core, exhibited the highest burn-up value with both methods. The calculations conducted using method 1 revealed a burn-up rate of 205.59 MWd/tHM for the B5 fuel element, while method 2 yielded a burn-up value of 5.40%. Experimental results were compared with previous simulation burn-up studies.
KW - Experimental burn-up analysis
KW - Fuel elements
KW - NDA method
KW - Triga Mark II reactor
UR - http://www.scopus.com/inward/record.url?scp=85190847761&partnerID=8YFLogxK
U2 - 10.1016/j.nucengdes.2024.113229
DO - 10.1016/j.nucengdes.2024.113229
M3 - Article
AN - SCOPUS:85190847761
SN - 0029-5493
VL - 424
JO - Nuclear Engineering and Design
JF - Nuclear Engineering and Design
M1 - 113229
ER -