TY - JOUR
T1 - Neutronics Assessment of Accident-Tolerant Fuel in Advanced Power Reactor 1400 (APR1400)
AU - Hartanto, D.
AU - Alshamsi, A.
AU - Alsuwaidi, A.
AU - Bilkhair, A.
AU - Hukal, H. A.
AU - Zubair, M.
N1 - Publisher Copyright:
© 2020. Atom Indonesia. All Rights Reserved.
PY - 2020
Y1 - 2020
N2 - Safety and reliability are the most desirable conditions that each nuclear power plant should improve. Since the Fukushima Daiichi accident, Accident-Tolerant Fuel (ATF) has been extensively researched to improve the performance of the nuclear fuel system. This paper presents the investigation of the ATF system from a neutronics perspective, which positively reflects on the performance of the APR-1400 nuclear power plant. Several advanced fuel candidates such as UC, U3Si2, and UN,which have better thermophysical properties than current UO2 nuclear fuel, have been considered. Meanwhile, advanced cladding candidates such as FeCrAl, Zr-alloy with coating, and SiC which can reduce or even eliminate the oxidation rate of current Zr-alloycladding have been adopted in this study. The Monte Carlo Serpent code, in conjunction with ENDF/B-VII.1 nuclear data library, has been used to calculate and evaluate the important neutronics parameters at the assembly level such as the fuel residence time, discharge burnup, kinetics parameters, pin power distribution, temperature reactivity feedbacks, and fissile evolution.The advanced fuels show betterneutronics performance than the current UO2 fuel. In addition, SiC provides optimum neutronic performance as cladding.
AB - Safety and reliability are the most desirable conditions that each nuclear power plant should improve. Since the Fukushima Daiichi accident, Accident-Tolerant Fuel (ATF) has been extensively researched to improve the performance of the nuclear fuel system. This paper presents the investigation of the ATF system from a neutronics perspective, which positively reflects on the performance of the APR-1400 nuclear power plant. Several advanced fuel candidates such as UC, U3Si2, and UN,which have better thermophysical properties than current UO2 nuclear fuel, have been considered. Meanwhile, advanced cladding candidates such as FeCrAl, Zr-alloy with coating, and SiC which can reduce or even eliminate the oxidation rate of current Zr-alloycladding have been adopted in this study. The Monte Carlo Serpent code, in conjunction with ENDF/B-VII.1 nuclear data library, has been used to calculate and evaluate the important neutronics parameters at the assembly level such as the fuel residence time, discharge burnup, kinetics parameters, pin power distribution, temperature reactivity feedbacks, and fissile evolution.The advanced fuels show betterneutronics performance than the current UO2 fuel. In addition, SiC provides optimum neutronic performance as cladding.
KW - APR1400
KW - Accident tolerant fuel
KW - ENDF/B-VII.1
KW - Neutronics assessment
KW - Serpent
UR - http://www.scopus.com/inward/record.url?scp=85098983571&partnerID=8YFLogxK
U2 - 10.17146/aij.2020.1073
DO - 10.17146/aij.2020.1073
M3 - Article
AN - SCOPUS:85098983571
SN - 2356-5322
VL - 46
SP - 177
EP - 186
JO - Atom Indonesia
JF - Atom Indonesia
IS - 3
ER -
