Sains Malaysiana 54(6)(2025): 1605-1616
http://doi.org/10.17576/jsm-2025-5406-15
Neutronic Investigation of the Fuji-12 MSR
Reactor with a Rectangular Core Configuration and Plutonium-Based Fuel
(Penyelidikan Neutronik Reaktor MSR
Fuji-12 dengan Konfigurasi Teras Segi Empat dan Bahan Api Berasaskan Plutonium)
RATNA DEWI SYARIFAH1,*,
AHMAD MUZAKI MABRURI2, ZEIN HANIFAH1, FAJRI PRASETYA2,
ARTOTO ARKUNDATO1, LUTFI ROHMAN1 & WENNY MAULINA1
1Department of Physics, Universitas Jember, Kalimantan Street, No 37, Krajan Timur, Sumbersari
Subdistrict, Jember, East Java, 68121, Indonesia
2Department
of Nuclear Science and Engineering, Institut Teknologi Bandung, Bandung, 40132,
Indonesia
Diserahkan: 17 September 2024/Diterima: 21 Mac
2025
Abstract
A
neutronic investigation of the design of the FUJI-12 Molten Salt Reactor (MSR)
with a rectangular core configuration and plutonium-based fuel has been
conducted. MSR FUJI-12 is a reactor with molten salt fuel developed by Japan.
This reactor operates at a power of 350 MWt, an operating temperature of up to
980 K, and the capability to perform nuclide transmutation. The purpose of this
research was to investigate the optimal design of the MSR FUJI-12 with a rectangular
fuel channel lattice and plutonium-based fuel to achieve a neutronically safe design
capable of burning the remaining reactor-grade plutonium (RGP) and weapon-grade
plutonium (WGP) during reactor operation. In this research, the fuel
composition is based on fluoride salt LiF-BeF2-ThF4-UF4-PuF3.
The investigation was conducted using OpenMC neutronics code with the nuclear
data library ENDF/B-VII.1. The results show that the optimal composition for
RGP is 1.14% PuF3 and 0.60% PuF3 for RGP. In addition,
the burn-up ratio of Pu239 in RGP is 44.3% and 61.1% for WGP. The
results of the FIR analysis show that the WGP and RGP cause a very significant
reduction in plutonium because the cleavage process is dominated by fissile
plutonium. In addition, the changes in PuF3 composition in WGP and
RGP affect the neutron reaction characteristics, including macroscopic cross-section,
neutron spectrum flux, total reaction rate, neutron flux, and power distribution
in axial and radial directions.
Keywords:
MSR FUJI-12; OpenMC; plutonium; rectangular; transmutation
Abstrak
Penyelidikan ke atas reka bentuk neutronik Reaktor Garam
Lebur (MSR) FUJI-12 dengan konfigurasi teras segi empat tepat dan bahan api berasaskan
plutonium telah dijalankan. MSR FUJI-12 ialah reaktor dengan bahan api garam
cair yang dibangunkan oleh Jepun. Reaktor ini beroperasi dengan kuasa 350 MWt,
mempunyai suhu operasi yang tinggi sehingga 980 K dan mampu menjalankan proses
transmutasi nuklida. Penyelidikan ini bertujuan untuk meneroka reka bentuk
optimum FUJI-12 MSR dengan grid saluran bahan api segi empat tepat dan bahan
api berasaskan plutonium untuk mencapai reka bentuk selamat neutronik yang
mampu membakar sisa Reaktor Gred Plutonium (RGP) dan Gred Senjata Plutonium
(WGP) semasa reaktor operasi. Dalam penyelidikan ini, komposisi bahan api
adalah berdasarkan garam fluorida LiF-BeF2-ThF4-UF4-PuF3.
Penyelidikan telah dijalankan menggunakan kod neutronik OpenMC dengan
perpustakaan data nuklear ENDF/B-VII.1. Hasil kajian menunjukkan komposisi
optimum untuk RGP ialah 1.14% PuF3 dan 0.60% PuF3 untuk
RGP. Di samping itu, nisbah pembakaran Pu239 dalam RGP ialah 44.3%
dan 61.1% untuk WGP. Hasil analisis FIR menunjukkan bahawa WGP dan RGP
menyebabkan pengurangan plutonium yang sangat ketara kerana proses pembelahan
didominasi oleh plutonium fisil. Di samping itu, perubahan dalam komposisi PuF3 dalam WGP dan RGP mempengaruhi ciri-ciri tindak balas neutron, termasuk keratan
rentas makroskopik, fluks spektrum neutron, kadar tindak balas jumlah, fluks
neutron dan pengagihan kuasa dalam arah paksi dan jejari.
Kata
kunci: MSR FUJI-12; OpenMC; plutonium; segi empat
tepat; transmutasi
RUJUKAN
Adam, L. 2016. Dinamika
sektor kelistrikan di Indonesia: Kebutuhan dan performa penyediaan. Jurnal
Ekonomi Pembangunan LIPI 24(1): 29-41.
https://doi.org/10.14203/JEP.24.1.2016.29–41
Aji, I.K. 2014.
Analisis kecepatan aliran fluida bahan bakar terhadap karakteristik kinetika
neutronik pada molten salt reactor FUJI-12. Thesis. Bandung Institute of
Technology (Unpublished).
Aji, I.K. &
Waris, A. 2010. Studi Pemanfaatan Plutonium Sebagai Bahan Bakar pada Molten
Salt Reactor.
https://pdfcoffee.com/studi-pemanfaatan-plutonium-sebagai-bahan-bakar-pada-molten-salt-reactor-fuji-12-indarta-kuncoro-aji-2010-pdf-free.html
Dian Perkasa.
2018. Analysis neutronik Molten Salt Reactor (MSFR). Bandung Institute of
Technology (Unpublished).
Goldberg, S.M.
& Rosner, R. 2011. Nuclear Reactors: Generation to Generation. Cambridge:
American Academy of Arts and Sciences.
Kementerian
Energi dan Sumber Daya Mineral. 2021. Rencana Usaha Penyediaan Tenaga
Listrik PT Perusahaan Listrik Negara (PERSERO) Tahun 2021 - Tahun 2030 -
Pengesahan 2021.
chrome-extension://efaidnbmnnnibpcajpcglclefindmkaj/https://jdih.esdm.go.id/common/dokumen-external/Abstrak%20Kepmen%20ESDM%20No.%20188.K_HK.02-MEM.L-2021.pdf
Kementerian
Energi dan Sumber Daya Mineral. 2008. Hingga 2030, Permintaan Energi Dunia
Meningkat 45%.
https://www.esdm.go.id/id/media-center/arsip-berita/hingga-2030-permintaan-energi-dunia-meningkat-45-
Mabruri, A.M.,
Syarifah, R.D., Aji, I.K., Arkundato, A. & Trianti, N. 2024. Validation of
OpenMC code for low-cycle and low-particle simulations in the neutronic
calculation criticality k-eff low-cycle MSR FUJI-12 OpenMC corresponding author. Jurnal Ilmu Fisika 16(2): 107-117.
https://doi.org/10.25077/10.25077/jif.16.2.107-117.2024
Mabruri, A.M.,
Syarifah, R.D., Aji, I.K., Hanifah, Z., Arkundato, A. & Jatisukamto, G.
2022. Neutronic analysis on Molten Salt Reactor FUJI-12 using 235U as fissile
material in LiF-BeF2-UF4 fuel. Eastern-European Journal of Enterprise
Technologies 5(8-119): 6-12. https://doi.org/10.15587/1729-4061.2022.265798
Nugraha, D.B.,
Harto, A.W. & Sihana. 2017. Moderator to fuel ratio and uranium fraction
analysis of square lattice molten salt transatomic power. J. Tek. Reaktor.
Nukl. 19(1): 1-10.
Prasetya, F.,
Mabruri, A.M., Karomah, I., Syarifah, R.D., Aji, I.K. & Trianti, N. 2024.
Validation of OpenMC code criticality value calculation for GFR reactor with
UN-PuN fuel. Journal of Physics: Conference Series 2734(1): 012065.
https://doi.org/10.1088/1742-6596/2734/1/012065
Prasetya, F.,
Syarifah, R.D., Karomah, I., Aji, I.K. & Trianti, N. 2024. A comparative
analysis of gas-cooled fast reactor using heterogeneous core configurations
with three and five fuel variations. Eastern-European Journal of Enterprise
Technologies 1(8(127)): 6-17.
https://doi.org/10.15587/1729-4061.2024.298202
Rykhlevskii,
A., Lindsay, A. & Huf, K. 2017. Online reprocessing simulation for
thorium-fueled molten salt breeder reactor. Transactions of the American
Nuclear Society 117: 239-242.
Syarifah, R.D.,
Nasrullah, M., Prasetya, F., Mabruri, A.M., Arkundato, A., Jatisukamto, G.
& Handayani, S. 2024a. Analysis of variation minor actinide pin
configurations Np-237, AM-241, and Cm-244 in UN-PuN fueled pressurized water
reactor. EUREKA, Physics and Engineering 1(1): 36-46.
https://doi.org/10.21303/2461-4262.2024.003048
Syarifah, R.D.,
Prasetya, F., Mabruri, A.M., Arkundato, A. & Trianti, N. 2024b. The effect
of adding minor actinide fuel rods on GFR reactor in radiopharmaceutical waste
production using OpenMC program. Science and Technology Indonesia 9(4):
857-865. https://doi.org/10.26554/sti.2024.9.4.857-865
Syarifah, R.D.,
Putri, B.A., Aji, I.K. & Mabruri, A.M. 2024c. Neutronic analysis on Molten
Salt Reactor (MSR) using OpenMC code with variations of geometry core fueled by
LiF-BeF2-UF4. El-Cezeri Journal of Science and Engineering 11(2): 152-159.
https://doi.org/10.31202/ecjse.1364028
Waris, A., Aji,
I.K., Pramuditya, S., Widayani & Irwanto, D. 2016. Preliminary study on
LiF4-ThF4-PuF4 utilization as fuel salt of miniFUJI Molten Salt Reactor. Journal
of Physics: Conference Series 739(1): 012004.
https://doi.org/10.1088/1742-6596/739/1/012004
Waris, A., Aji,
I.K., Pramuditya, S., Novitrian, Permana, S. & Su’Ud, Z. 2015. Comparative
studies on plutonium and minor actinides utilization in small Molten Salt
Reactors with various powers and core sizes. Energy Procedia 71: 62-68.
https://doi.org/10.1016/j.egypro.2014.11.855
Waris, A.,
Pramuditya, A., Basar, K., Aji, I.K., Wirawan, R., Monado, F. & Subkhi,
M.N. 2014. Comparative studies on plutonium and 233U utilization in miniFUJI
MSR. Paper Presented at 2014 International Conference on Physics of
Reactors, PHYSOR 2014, Kyoto, Japan.
Waris, A.,
Richardina, V., Aji, I.K., Permana, S. & Su’Ud, Z. 2013. Preliminary study
on plutonium and minor actinides utilization in thorims-nes minifuji reactor. Energy
Conversion and Management 72: 27-32.
https://doi.org/10.1016/j.enconman.2013.03.005
Waris, A., Aji,
I.K., Novitrian, Kurniadi, R. & Su’ud, Z. 2012. Plutonium and minor
actinides utilization in thorium Molten Salt Reactor. AIP Conference
Proceedings 1448: 115-118. https://doi.org/10.1063/1.4725445
Waris, A., Aji,
I.K., Yulianti, Y., Shafii, A., Taufiq, I. & Su’ud, Z. 2010. Comparative
study on 233 U and plutonium utilization in Molten Salt Reactor. Indonesian
Journal of Physics 21(3): 77-81.
Wulandari, C.,
Waris, A. & Permana, S. 2021. Comparatives studies in Molten Salt Reactor
FUJI-U3 with various power. Journal of Physics: Conference Series 1772(1): 012027. https://doi.org/10.1088/1742-6596/1772/1/012027
Wulandari, C.,
Waris, A., Permana, S. & Pramuditya, S. 2022. Evaluating the JEFF 3.1,
ENDF/B-VII.0, JENDL 3.3, and JENDL 4.0 nuclear data libraries for a small
100 MWe Molten Salt Reactor with plutonium fuel. Nuclear Science and
Techniques 33(12): 165. https://doi.org/10.1007/s41365-022-01141-8
Wulandari, C.,
Sofyan, A., Waris, A. & Permana, S. 2021. Natural uranium utilization in
FUJI-U3 Molten Salt Reactor. Journal of Physics: Conference Series 1772(1): 012023. https://doi.org/10.1088/1742-6596/1772/1/012023
Wulandari, C.,
Waris, A., Permana, S. & Pramuditya, S. 2021. Neutronic performances of 100
MWe MSR with weapon grade plutonium fuel. Journal of Physics: Conference
Series 1949(1): 012019. https://doi.org/10.1088/1742-6596/1949/1/012019
Wulandari, C.,
Waris, A., Permana, S. & Pramuditya, S. 2019. Plutonium and minor actinides
utilization in FUJI-U1 Molten Salt Reactor. Journal of Physics: Conference
Series 1204(1): 012132. https://doi.org/10.1088/1742-6596/1204/1/012132
Wulandari, C.,
Waris, A., Pramuditya, S., Asril, P.A.M. & Novitrian. 2017. Study on utilization
of super grade plutonium in Molten Salt Reactor FUJI-U3 using CITATION code. Journal
of Physics: Conference Series 877(1): 012021.
https://doi.org/10.1088/1742-6596/877/1/012021
Yamamoto, T.,
Mitachi, K. & Suzuki, T. 2005. Steady state analysis of small Molten Salt
Reactor * (effect of fuel salt flow on reactor characteristics). JSME
International Journal 48(3): 610-617.
*Pengarang untuk surat-menyurat; email: rdsyarifah.fmipa@unej.ac.id