Effect of Protactinium-231 (Pa-231) Addition on Effective Multiplication Factor Value of ThN-U233N Fueled PWR Reactor
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Published:
Dec 8, 2023
Keywords:
OpenMC; Protactinium-231; PWR; ThN-U233N, OpenMC, Pressurized Water Reactor, Protactinium-231
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Abstract
This study aims to determine the optimum percentage of addition of protactinium-231 in a ThN-U233N fueled PWR reactor.In ThN-U233N, uranium-233 is used as the fissile material. Pa-231 as burnable poisson is added to ThN-U233N fuel to reduce the keff value. In this research conducted benchmarking keff values of OpenMC and SRAC codes, homogeneous and heterogeneous core configurations, and the addition of Pa-231 in ThN-U233N fuel. Neutronic analysis was performed using the OpenMC code. In the homogeneous core configuration, the enrichment percentage of U-233 is varied by 1%-15%. Meanwhile, the heterogeneous core configuration uses 3 variations of ring geometry and fuel. The results of the benchmarking of the OpenMC and SRAC code keff values show a maximum error of 1,906%. The homogeneous core configuration produces the optimum value for U-233 enrichment of 3%. Meanwhile, the optimum value of the heterogeneous core configuration is achieved in ring geometry F1 = F2 = F3 = 3 rings with enrichment of U-233 at F1 = 0,5%, F2 = 3%, F3 = 5,5% and addition of Pa-231 of 1.5%. The optimum calculation results has an excess reactivity value 8.37%.
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“Effect of Protactinium-231 (Pa-231) Addition on Effective Multiplication Factor Value of ThN-U233N Fueled PWR Reactor”. Jurnal Ilmu Fisika dan Pembelajarannya (JIFP) 7, no. 2 (December 8, 2023): 23–32. Accessed April 19, 2025. https://jurnal.radenfatah.ac.id/index.php/jifp/article/view/19159.
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How to Cite
“Effect of Protactinium-231 (Pa-231) Addition on Effective Multiplication Factor Value of ThN-U233N Fueled PWR Reactor”. Jurnal Ilmu Fisika dan Pembelajarannya (JIFP) 7, no. 2 (December 8, 2023): 23–32. Accessed April 19, 2025. https://jurnal.radenfatah.ac.id/index.php/jifp/article/view/19159.
References
Ardianingrum, A. (2022). Perbandingan Nilai Faktor Multiplikasi dan Densitas Daya pada PWR Berbahan Bakar Th(U-233)N, Th(U-233)C, dan Th(U-233)O2 Menggunakan Kode SRAC-COREBN 2D. Skripsi. Universitas Jember.
Athiqoh, F., Budi, W. S., Anam, C., & Tjiptono, T. W. (2014). Distribusi Fluks Neutron sebagai Fungsi Burn-Up Bahan Bakar pada Reaktor Kartini. Youngster Physics Journal, 3(2), 107–112.
Dibyo, S. (2007). Studi Karakteristik Pressurizer pada PWR. Prosiding PPI - PDIPTN, 179–185.
Gunoto, P., & Sofyan, S. (2020). Perancangan Pembangkit Listrik Tenaga Surya 100 Wp untuk Penerangan Lampu di Ruang Selasar Fakultas Teknik Universitas Riau Kepulauan. Sigma Teknika, 3(2), 96–106. https://doi.org/10.33373/sigma.v3i2.2754
Irfan, M., Bura, R. O., & Wahyudi, D. (2020). Konsep Teknologi Reaktor Nuklir sebagai Sistem Propulsi Kapal Perang Logistik Landing Platform Dock. Teknologi Daya Gerak, 3(1), 1–24. http://jurnalprodi.idu.ac.id/index.php/TDK/article/view/533
Koloay, A. C., Tumaliang, H., & Pakiding, M. (2018). Perencanaan dan Pemenuhan Kebutuhan Energi Listrik di Kota Bitung. Jurnal Teknik Elektro dan Komputer, 7(3), 285–294.
Ngadenin, Syaeful, H., Widana, K. S., & Nurdin, M. (2014). Eksplorium Potensi Thorium dan Uranium di Kabupaten Bangka Barat Potency of Thorium and Uranium. 35(2), 69–84.
Putri, C. D., Monado, F., & Ariani, M. (2022). Analisis Neutronik Kekritisan Teras Reaktor Nuscale Berbahan Bakar UO2 dengan Menggunakan Software OpenMC. JoP, 8(1), 43–50.
Rajagukguk, S. P., Bakhri, S., & Surbakti, T. (2021). Perhitungan Inventori Nuklida pada Pin Bahan Bahan Reaktor PWR. Sigma Epsilon, 25(2), 92–102.
Romano, P. K., & Forget, B. (2013). The OpenMC Monte Carlo Particle Transport Code. Annals of Nuclear Energi, 51, 274–281.
Romano, P. K., Horelik, N. E., Herman, B. R., Nelson, A. G., Forget, B., & Smith, K. (2014). OpenMC: A State-of-the-Art Monte Carlo Code for Research and Development. 06016. https://doi.org/10.1051/snamc/201406016
Sari, A. K., Syarifah, R. D., & Arkundato, A. (2022). Preliminary study of 300 MWth pressurized water reactor with carbide fuel with addition neptunium 237 using SRAC-COREBN code. AIP Conference Proceedings.
Shafii, M. A. (2013). Beberapa Metode Penyelesaian Persamaan Transport Neutron dalam Reaktor Nuklir. Jurnal Ilmu Dasar, 14(2), 59–65.
Subkhi, M. N., Su’ud, Z., Waris, A., & Permana, S. (2015). Studi Desain Reaktor Air Bertekanan (PWR) Berukuran Kecil Berumur Panjang Berbahan Bakar Thorium. Jurnal ISTEK, 9(1), 32–49.
Suhaemi, T. (2016). Pembangunan Pembangkit Listrik Tenaga Nuklir (PLTN) Menopang Kebutuhan Eenergi Listrik Nasional. Seminar Nasional TEKNOKA_FT UHAMKA, 1, 162–170. https://journal.uhamka.ac.id/index.php/teknoka/article/view/809
Syarifah, R. D., Aula, M. H., Ardianingrum, A., Janah, L. N., & Maulina, W. (2022). Comparison of Thorium Nitride and Uranium Nitride Fuel on Small Modular Pressurized Water Reactor in Neutronic Analysis Using SRAC Code. Eastern-European Journal of Enterprise Technologies, 2(8–116), 21–28. https://doi.org/10.15587/1729-4061.2022.255849
Syarifah, R. D., Sari, A. K., Arkundato, A., Irwanto, D., & Su’ud, Z. (2022). Neutronics Analysis of UN-PuN Fuel for 300 MW Pressurized Water Reactor Using SRAC-COREBN Code. Eureka: Physics and Engineering, 6(43).
Syarifah, R. D., & Suud, Z. (2015). The prospect of uranium nitride (UN) and mixed nitride fuel (UN-PuN) for pressurized water reactor. AIP Conference Proceedings, 1677, 1–5. https://doi.org/10.1063/1.4930788
Athiqoh, F., Budi, W. S., Anam, C., & Tjiptono, T. W. (2014). Distribusi Fluks Neutron sebagai Fungsi Burn-Up Bahan Bakar pada Reaktor Kartini. Youngster Physics Journal, 3(2), 107–112.
Dibyo, S. (2007). Studi Karakteristik Pressurizer pada PWR. Prosiding PPI - PDIPTN, 179–185.
Gunoto, P., & Sofyan, S. (2020). Perancangan Pembangkit Listrik Tenaga Surya 100 Wp untuk Penerangan Lampu di Ruang Selasar Fakultas Teknik Universitas Riau Kepulauan. Sigma Teknika, 3(2), 96–106. https://doi.org/10.33373/sigma.v3i2.2754
Irfan, M., Bura, R. O., & Wahyudi, D. (2020). Konsep Teknologi Reaktor Nuklir sebagai Sistem Propulsi Kapal Perang Logistik Landing Platform Dock. Teknologi Daya Gerak, 3(1), 1–24. http://jurnalprodi.idu.ac.id/index.php/TDK/article/view/533
Koloay, A. C., Tumaliang, H., & Pakiding, M. (2018). Perencanaan dan Pemenuhan Kebutuhan Energi Listrik di Kota Bitung. Jurnal Teknik Elektro dan Komputer, 7(3), 285–294.
Ngadenin, Syaeful, H., Widana, K. S., & Nurdin, M. (2014). Eksplorium Potensi Thorium dan Uranium di Kabupaten Bangka Barat Potency of Thorium and Uranium. 35(2), 69–84.
Putri, C. D., Monado, F., & Ariani, M. (2022). Analisis Neutronik Kekritisan Teras Reaktor Nuscale Berbahan Bakar UO2 dengan Menggunakan Software OpenMC. JoP, 8(1), 43–50.
Rajagukguk, S. P., Bakhri, S., & Surbakti, T. (2021). Perhitungan Inventori Nuklida pada Pin Bahan Bahan Reaktor PWR. Sigma Epsilon, 25(2), 92–102.
Romano, P. K., & Forget, B. (2013). The OpenMC Monte Carlo Particle Transport Code. Annals of Nuclear Energi, 51, 274–281.
Romano, P. K., Horelik, N. E., Herman, B. R., Nelson, A. G., Forget, B., & Smith, K. (2014). OpenMC: A State-of-the-Art Monte Carlo Code for Research and Development. 06016. https://doi.org/10.1051/snamc/201406016
Sari, A. K., Syarifah, R. D., & Arkundato, A. (2022). Preliminary study of 300 MWth pressurized water reactor with carbide fuel with addition neptunium 237 using SRAC-COREBN code. AIP Conference Proceedings.
Shafii, M. A. (2013). Beberapa Metode Penyelesaian Persamaan Transport Neutron dalam Reaktor Nuklir. Jurnal Ilmu Dasar, 14(2), 59–65.
Subkhi, M. N., Su’ud, Z., Waris, A., & Permana, S. (2015). Studi Desain Reaktor Air Bertekanan (PWR) Berukuran Kecil Berumur Panjang Berbahan Bakar Thorium. Jurnal ISTEK, 9(1), 32–49.
Suhaemi, T. (2016). Pembangunan Pembangkit Listrik Tenaga Nuklir (PLTN) Menopang Kebutuhan Eenergi Listrik Nasional. Seminar Nasional TEKNOKA_FT UHAMKA, 1, 162–170. https://journal.uhamka.ac.id/index.php/teknoka/article/view/809
Syarifah, R. D., Aula, M. H., Ardianingrum, A., Janah, L. N., & Maulina, W. (2022). Comparison of Thorium Nitride and Uranium Nitride Fuel on Small Modular Pressurized Water Reactor in Neutronic Analysis Using SRAC Code. Eastern-European Journal of Enterprise Technologies, 2(8–116), 21–28. https://doi.org/10.15587/1729-4061.2022.255849
Syarifah, R. D., Sari, A. K., Arkundato, A., Irwanto, D., & Su’ud, Z. (2022). Neutronics Analysis of UN-PuN Fuel for 300 MW Pressurized Water Reactor Using SRAC-COREBN Code. Eureka: Physics and Engineering, 6(43).
Syarifah, R. D., & Suud, Z. (2015). The prospect of uranium nitride (UN) and mixed nitride fuel (UN-PuN) for pressurized water reactor. AIP Conference Proceedings, 1677, 1–5. https://doi.org/10.1063/1.4930788