Perhitungan Shutdown Margin Teras NuScale Menggunakan OpenMC

Hadi Razaqiyanto, Mohammad Ali Shafii, Helen Raflis

Abstract


One of the important reactor safety parameters to study is the issue of shutdown margin (SDM). This study aims to obtain an effective safety design of the NuScale reactor in reviewing the SDM value parameter. SDM calculations are performed using OpenMC, which is a programming code based on the Monte Carlo method. OpenMC is an open source calculation code that has the advantage of access to modifications to the reactor core geometry design. The type of reactor used in this simulation is the NuScale Small Modular Reactor (SMR) which is a Pressurized Water Reactor (PWR) type of reactor. The NuScale core simulation was designed in accordance with the General Design Criterion (GDC), which is a core arrangement that has a Control Rod Assemblies (CRA) regulating bank (RB) and CRA shutdown bank (SB) and UO2 fuel with an enrichment of <4.9%. From the calculation results, the SDM value of NuScale is 17743 pcm. This NuScale core SDM value indicates that the NuScale reactor under study complied with the sufficient safety design limits for all power levels and operating modes.


Keywords


CRA, NuScale, OpenMC, SDM, Simulasi

Full Text:

PDF

References


BAPETEN. (2012), “Kepala badan pengawas tenaga nuklir republik indonesia”, Standar Kegiatan Usaha Dan Standar Produk Pada Penyelenggaraan Perizinan Berusaha Berbasis Risiko Sektor Ketenaganukliran, pp. 2–3.

NuScale Power, L. (2012), “Rod Ejection Accident Methodology”, United States Nuclear Regulatory Commission.

NuScale Power, L. (2020), NuScale Plant Design Overview, Washington, OC, USA.

Reyes Jr, J.. and Lorenzini, P. (2010), “NuScale Power: A modular”, Nuclear News, Vol. 53, p. 7.

Romano, P.K. and Forget, B. (2012), “The OpenMC Monte Carlo particle transport code”, Annals of Nuclear Energy, Vol. 51, pp. 274–281, doi: 10.1016/j.anucene.2012.06.040.

Romano, P.K., Horelik, N.E., Herman, B.R., Nelson, A.G., Forget, B. and Smith, K. (2015), “OpenMC: A state-of-the-art Monte Carlo code for research and development”, Annals of Nuclear Energy, Elsevier Ltd, Vol. 82, pp. 90–97, doi: 10.1016/j.anucene.2014.07.048.

Rr, A.P.R. and Sahala M, K. (2012), “Studi Prospek PLTN Daya Kecil Nuscale di Indonesia”, Jurnal Pengembangan Energi Nuklir, Vol. 14 No. 1, pp. 57–64.

Waluyo, A. and Khakim, A. (2019), “Perhitungan Reaktivitas Batang Kendali HTR-10 dengan Menggunakan SCALE”, Seminar Nasional Infrastruktur Energi Nuklir 2019, Pontianak, pp. 313–319.




DOI: https://doi.org/10.25077/jfu.12.4.512-517.2023

Refbacks

  • There are currently no refbacks.


Creative Commons License
This work is licensed under a Creative Commons Attribution-NonCommercial 4.0 International License

Published by:

Departemen Fisika, FMIPA Universitas Andalas

Kampus Unand Limau Manis Padang Sumatera Barat 25163

Telepon 0751-73307

Email:jfu@sci.unand.ac.id