Analisis Neutronik Reaktor PeLUIt-40 menggunakan HTR-Code Package

Amarillo, Ramli Zhafran (2026) Analisis Neutronik Reaktor PeLUIt-40 menggunakan HTR-Code Package. Sarjana thesis, UIN Sunan Gunung Djati Bandung.

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Abstract

INDONESIA: PeLUIt-40 (Pembangkit Listrik dan Uap Panas Industri) merupakan reaktor pebble-bed jenis HTGR (High Temperature Gas-cooled Reactor) berdaya 30 MWt yang dikembangkan oleh BRIN dan ITB sebagai desain konseptual dan aplikasi PLTN serta industri nuklir di Indonesia. Studi ini berfokus pada aspek neutronik pada reaktor PeLUIt-40 untuk mesh terbatas hingga bagian RPV dengan penelitian menggunakan HTR-Code Package (HCP). Oleh karena itu, penelitian ini bertujuan untuk menganalisis karakteristik neutronik reaktor PeLUIt-40, membandingkan pengaruh skema pergantian bahan bakar OTTO (Once Through-Then-Out) dan Multipass (MEDUL), serta menganalisis distribusi fluks neutron hingga batas Reactor Pressure Vessel (RPV). Parameter neutronik yang dianalisis meliputi faktor multiplikasi efektif (keff), reaktivitas, distribusi fluks neutron cepat dan termal, distribusi rapat daya, konsentrasi Xenon-135, serta Displacement Per Atom (DPA). Hasil simulasi menunjukkan bahwa skema OTTO mampu mempertahankan kondisi kritis selama 3700 hari pada variasi daya 10 MWt, 20 MWt, dan 30 MWt, sedangkan skema Multipass mengalami penurunan keff hingga subkritis dan hanya beroperasi selama 1628 Hari pada variasi daya 10 MWt dan 30 MWt. Bentuk tren parameter neutronik menunjukkan perilaku yang sesuai dengan bagaimana skema pergantian bahan bakar dilakukan dan keamanan radiasi pada bagian luar teras aman dengan hasil DPA yang kecil selama masa operasi. ENGLISH: PeLUIt-40 (Industrial Power and Steam Generator) is a 30 MWt pebble-bed High-Temperature Gas-cooled Reactor (HTGR) developed by BRIN and ITB as a conceptual design and application for nuclear power plants and the nuclear industry in Indonesia. This study focuses on the neutronic aspects of the PeLUIt-40 reactor for a limited mesh extending to the Reactor Pressure Vessel (RPV) region, utilizing the HTR-Code Package (HCP) for the research. Therefore, this research aims to analyze the neutronic characteristics of the PeLUIt-40 reactor, compare the effects of the OTTO (Once Through-Then-Out) and Multipass (MEDUL) fuel loading schemes, and analyze the neutron flux distribution up to the RPV boundary. The neutronic parameters analyzed include the effective multiplication factor (keff), reactivity, fast and thermal neutron flux distributions, power density distribution, Xenon-135 concentration, and Displacements Per Atom (DPA). Simulation results show that the OTTO scheme is capable of maintaining critical conditions for 3700 days at power variations of 10 MWt, 20 MWt, and 30 MWt, whereas the Multipass scheme experiences a decrease in keff to subcritical levels and only operates for 1628 days at power variations of 10 MWt and 30 MWt. The trend of the neutronic parameters exhibits behavior consistent with the applied fuel replacement schemes, and radiation safety outside the core is maintained, as indicated by low DPA values throughout the operating period.

Item Type: Thesis (Sarjana)
Uncontrolled Keywords: PeLUIt-40; HTR-Code Package; HTGR; pebble-bed reactor; neutronik; fuel management; neutron flux
Subjects: Physics
Modern Physics > Atomic and Nuclear Physics
Applied Physics
Applied Physics > Nuclear Engineering
Applied Physics > Nuclear Reactors
Divisions: Fakultas Sains dan Teknologi > Program Studi Fisika
Depositing User: Ramli Zhafran Amarillo
Date Deposited: 11 Aug 2026 03:31
Last Modified: 11 Aug 2026 03:31
URI: https://digilib.uinsgd.ac.id/id/eprint/138019

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