Neutronic Analysis of the AP1000 Fuel Assembly with Accident Tolerant Cladding Materials
Abstract
Keywords
Supporting Institution
Project Number
Thanks
References
- [1] Liang, Y., Lan, B., Zhang, Q., Seidl, M., Wang, X., “Neutronic analysis of silicon carbide Cladding-ATF fuel combinations in small modular reactors”, Annals Nuclear Energy, 173: 109120, (2022).
- [2] Younan, S., Novog, D., “Assessment of Neutronic Characteristics of Accident-Tolerant Fuel and Claddings for CANDU Reactors”, Science Technology Nuclear Installation, (2018).
- [3] Chen, S., Yuan, C., “Neutronic Analysis on Potential Accident Tolerant Fuel-Cladding Combination U3Si2-FeCrAl”, Science Technology Nuclear Installation, (2017).
- [4] Alrwashdeh, M., Alameri, S.A., “Preliminary neutronic analysis of alternative cladding materials for APR-1400 fuel assembly”, Nuclear Engineering Design, 384: 111486, (2021).
- [5] Sembiring, T.M., Pinem, S., “The validation of the NODAL3 code for static cases of the PWR benchmark core”, Jurnal Nuklir Sains Teknologi Ganendra, 15(2): 82–92, (2012).
- [6] Pinem, S., Sembiring, T.M., Liem, P.H., “NODAL3 Sensitivity Analysis for NEACRP 3D LWR Core Transient Benchmark (PWR)”, Science Technology Nuclear Installation, 1–11, (2016).
- [7] Sembiring, T.M., Pinem, S., Liem, P.H., “Analysis of NEA-NSC PWR Uncontrolled Control Rod Withdrawal at Zero Power Benchmark Cases with NODAL3 Code”, Science Technology Nuclear Installation, (2017).
- [8] Pinem, S., Sembiring, T.M., Liem, P.H., “The verification of coupled neutronics thermal-hydraulics code NODAL3 in the PWR rod ejection benchmark”, Science Technology Nuclear Installation, 1–9 (2014).
Details
Primary Language
English
Subjects
Nuclear Physics
Journal Section
Research Article
Authors
Wahid Luthfı
*
0000-0002-4499-3433
Indonesia
Surian Pinem
0000-0001-6990-1059
Indonesia
Farisy Yogatama Sulistyo
0000-0002-6222-7927
Indonesia
Tukiran Surbakti
0000-0002-4081-774X
Indonesia
Early Pub Date
April 20, 2024
Publication Date
December 1, 2024
Submission Date
July 26, 2023
Acceptance Date
March 18, 2024
Published in Issue
Year 2024 Volume: 37 Number: 4
Cited By
Neutronic analysis for withdrawal of TRIGA MARK II reactor control rods using OpenMC program
Annals of Nuclear Energy
https://doi.org/10.1016/j.anucene.2025.111330Preliminary Neutronic Analysis of UN Fuel and SiC Cladding for Advanced Accident Tolerant Fuel in LWRs
International Journal of Advanced Nuclear Reactor Design and Technology
https://doi.org/10.1016/j.jandt.2026.03.007