PRELIMINARY STUDY OF FUEL DEPLETION IN AP1000 PWR REACTOR FOR FUEL ASSEMBLY LEVEL USING SRAC2006 CODE

• Main Author: Kurniawan, Agung
• Format: Final Project
• Language: Indonesia
• Online Access: https://digilib.itb.ac.id/gdl/view/84063
• Institution: Institut Teknologi Bandung

In the current era of technological advancement, the demand for energy is rapidly increasing. Therefore, there is a need for technology capable of producing large and sustainable amounts of energy. Nuclear reactors are a highly promising alternative energy source, offering long operational lifespans and competitive performance compared to fossil fuel-based energy for its high energy density. This study presents a preliminary analysis of fuel depletion in the Westinghouse AP1000 PWR reactor at the fuel assembly level. The power density used for the fuel assembly is adjusted according to different positions and enrichments within the AP1000 reactor core. The study aims to determine the burnup of the fuel assembly, including the waste generated at the end of the operational cycle. Simulations were conducted using the SRAC2006 code developed by JAERI, utilizing JENDL-4.0 nuclear data. The study was performed for several enrichment levels: 2.35%, 3.4%, and 4.45% by mass of Uranium-235. The results indicate that the fuel assembly with 2.35 w/o enrichment at the center of the core has the least remaining U-235 with the highest waste, indicating significant U-235 burnup. The percentage of U-235 remaining at the end of the cycle for fuel assemblies with 2.35 w/o, 3.4 w/o, and 4.45 w/o enrichment were 28.608%, 56.120%, and 78.593%, respectively. This study also identifies the production of new nuclides, including Plutonium, minor actinides, and long-lived fission products (LLFPs). The quantities produced vary depending on the enrichment level and the fuel assembly's position within the core.