Neutronic Analysis of the AP1000 Fuel Assembly with Accident Tolerant Cladding Materials

Year 2024, , 2012 - 2023, 01.12.2024

Wahid Luthfı , Surian Pinem , Farisy Yogatama Sulistyo , Tukiran Surbakti

https://doi.org/10.35378/gujs.1332751

Abstract

An alternative material for fuel cladding was required to prevent oxidation caused by interacting with steam, leading to improvement in core integrity. This study analyzes reactor physics parameters of various cladding material candidates for Pressurized Water Reactor (PWR) such as SS-304 austenitic stainless steel, FeCrAl alloy, APMT alloy, and silicon carbide (SiC) ceramic, as candidate Accident Tolerant Fuel (ATF). The neutronic parameters such as infinite multiplication factor (k-inf), and neutron spectrum, while temperature reactivity coefficient related to fuel temperature (DTC) and moderator temperature (MTC) is also considered, followed by a void coefficient of reactivity (VCR) of each candidate material were then compared with ZIRLO as a standard cladding material of AP1000. k-inf calculated by SRAC2006 is also compared to MCNP for various fuel assembly types. At the beginning of cycle (BOC), the 2.35% UO2 using SiC gives a higher kinf than ZIRLO at 937 pcm, while 4.45% UO2 with 88 IFBA & 9 PYREX at 796 pcm. FeCrAl, APMT, and SS-304 cladding gave a smaller k-inf compared to ZIRLO in the range of 11000-14000 pcm at 2.35% UO2 fuel assembly. The values of DTC, MTC, and VCR were still negative throughout the reactor operation which indicates that the inherent safety feature of alternative cladding was possible for this type of fuel assembly, especially for iron-based cladding material followed by an increase in fuel enrichment.

Keywords

Alternative cladding material, Accident tolerant fuel (ATF), K-inf, Coefficient of reactivity, SRAC2006

Supporting Institution

National Research and Innovation Agency (BRIN)

Project Number

DIPA- 124.01.1.690503/2022

Thanks

Thank you to the head of the Research Center for Nuclear Reactor Technology (PRTRN) Research Organization for Nuclear Energy (ORTN), National Research and Innovation Agency (BRIN) for supporting this research through DIPA 2022 No. DIPA- 124.01.1.690503/2022.

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