Investigation on Neutronic Parameters of the KLT-40S Reactor Core with U3Si2-FeCrAl using SCALE Code
Penulis/Author
ALIF AL MAHFUDZ (1); Dr. Ir. Alexander Agung, S.T., M.Sc., IPU. (2); Dr. Ir. Andang Widi Harto, M.T., IPU., ASEAN Eng. (3)
Tanggal/Date
2023
Kata Kunci/Keyword
Abstrak/Abstract
From a safety point of view, the fuel-cladding choice from the current design of the KLT-40S reactor still has a potential threat in the event of a loss-of-coolant accident (LOCA) which allows the formation of hydrogen gas. The concept of accident tolerant fuels (ATF) offers a variety of new safer fuel-cladding materials, one of which is the U3Si2-FeCrAl, a potential fuel-cladding combination according to various research sources. In this research, a study of neutronic parameters: (1) cycle length, (2) reactivity feedback coefficient, and (3) reactor proliferation resistance was performed with ATF material U3Si2-FeCrAl as fuel-cladding in the KLT-40S reactor core. Modeling and simulation of the ATF-fueled KLT-40S reactor core were performed using KENO-VI and TRITON modules from SCALE code. The results showed that the replacement of fuel-cladding material into ATF in the KLT-40S reactor resulted in a shorter cycle length, and the enrichment required to reproduce the original cycle length is above the safeguard limit. The fuel temperature, moderator temperature, and void reactivity coefficient are negative, although not as negative as the original. The spent fuel produced at the end of the cycle has good proliferation resistance, although not as good as the original.
Rumpun Ilmu
Teknik Nuklir (dan Atau Ilmu Nuklir Lain)
Bahasa Asli/Original Language
English
Level
Internasional
Status
Dokumen Karya
No
Judul
Tipe Dokumen
Aksi
1
Bukti under review.pdf
Bukti Under Review
2
18773-Article Text-67064-2-10-20230306.pdf
[PAK] Full Dokumen
3
Investigation on Neutronic Parameters of the KLT-40S Reactor Core with U3Si2-FeCrAl using SCALE Code.pdf
