Neutronic Analysis of Small Long-Life Pressurized Water Reactor Using (Th-U)O2 Fuels with Gd2O3 and Pa-231 as Burnable Poisons
Main Article Content
Abstract
The requirement for electricity increases with the growth of the human population. The existing power plants have not been able to fulfill all electricity requirements, especially in remote areas. The small long-life pressurized water reactor (PWR) is one of the solutions and innovations in nuclear technology that can produce electrical energy for a long time without refueling. This study aimed to analyze the neutronic of small long-life PWR that using Thorium-Uranium dioxide ((Th-U)O2) fuels with enriched Uranium-235 (U-235) and the addition of Gadolinium (Gd2O3) and Protactinium-231 (Pa-231) as the burnable poisons. The SRAC Code with the JENDL-4.0 nuclear data library had been used for the calculation method. In this study, the geometry of the two-dimensional (R-Z) reactor core with different fuel volume fraction was analyzed. Moreover, variations of the Uranium-235, Gadolinium, and Protactinium-231 fractions in the fuels were carried out. The result in this study was a PWR 420 MWt design using 60% Uranium dioxide fuel with enriched Uranium-235 of 10%-11%-12% and the addition of 0,0125% Gadolinium and 1,0% Protactinium-231 as the burnable poisons that could operate for thirteen years without refueling. The small long-life PWR design could produce a power density of 85,1 watts/cc with the reactivity for less than 4,6% dk/k.
Downloads
Download data is not yet available.
Article Details
How to Cite
Hariyanto, D., Yuningsih, N., & Permana, S. (2020). Neutronic Analysis of Small Long-Life Pressurized Water Reactor Using (Th-U)O2 Fuels with Gd2O3 and Pa-231 as Burnable Poisons. Indonesian Journal of Physics, 31(1), 10 - 15. https://doi.org/10.5614/itb.ijp.2020.31.1.2
Section
Articles
References
[1] A. C. Adi et al., Handbook of Energy and Economic Statistic of Indonesia. Center for Data and Information on Energy and Mineral Resources, Ministry of Energy and Mineral Resources Republic of Indonesia, Jakarta, 2018.
[2] Yudiarto et al., Indonesia Energy Outlook 2018. Center of Assessment for Process and Energy Industry, Jakarta, 2018.
[3] Sub-Directorate on Investment of Electricity, The Investment Opportunities On Electricity Sector 2017-2021. Directorate General of Electricity, Jakarta, 2016.
[4] M. N. Subkhi, Z. Su’ud, and A. Waris, Netronic Design of Small Long-Life PWR using Thorium Cycle, Advanced Materials Research, 772, 524-529, 2013.
[5] M. N. Subkhi, Z. Su’ud, A. Waris, and S. Permana, Design Concept of Small Long-Life PWR Using Square and Hexagonal Thorium Fuel, ARPN Journal of Engineering and Applied Sciences, 11(2), 830-832, 2016.
[6] T. Takei and A. Yamaji, Core Design of PWR-type Seed-blanket Core Breeder Reactor with Tightly Packed Fuel Assembly, Nuclear Engineering and Design, 333, 45-54, 2018.
[7] C. Juan, Z. Tao, and R. Ke, The Energy-Saving Diagnosis of PWR Nuclear Power Station Based on The Thermo-Economic Analysis Model, 18th Int. Conf. on Nuclear Engineering (May 17-21, 2010, Xi'an, China), 1, 2010.
[8] D. Irwanto and Z. Su’ud, Design Study of Long Life Thorium-based Pressurized Water Reactor (PWR) Using Annular Fuel System and Protactanium as Burnable Poison, Proceedings of Asian Physics Symposium (December 7-8, 2005, Bandung, Indonesia), 307-313, 2006.
[9] M. N. Subkhi, Z. Su’ud, and A. Waris, Design Study of Long-Life PWR using Thorium Cycle, The 3rd Int. Conf. on Advances in Nuclear Science and Engineering (November 14-17, 2011, Denpasar, Bali),101-106, 2012.
[10] Rouf and Z. Su’ud, Conceptual Core Analysis of Long Life PWR Utilizing Thorium-Uranium Fuel Cycle, Journal of Physics: Conference Series, 739(1), 1-7, 2016.
[11] S. Permana, N. Takaki, and H. Sekimoto, Preliminary Study on Feasibility of Large and Small Water Cooled Thorium Breeder Reactor in Equilibrium States, Progress in Nuclear Energy, 50, 320-324, 2008.
[12] T.K. Kim and T.J. Downar, Thorium Fuel Performance in a Tight Pitch Light Water Reactor Lattice, Nuclear Technology, 138(1), 17-29, 2007.
[13] M. Lung and O. Gremm, Perspectives of the Thorium Fuel Cycle, Nuclear Engineering and Design, 180(2), 133-146, 1998.
[14] T. Ünak, What is the Potential Use of Thorium in the Future Energy Production Technology?, Progress in Nuclear Energy, 37(1-4), 137-144, 2000.
[15] S. Permana, N. Takaki, and H. Sekimoto, Feasible Region of Design Parameters for Water Cooled Thorium Breeder Reactor, Journal of Nuclear Science and Technology, 44(7), 946-957, 2007.
[16] H. Akie, Y. Ishiguro, and Y. Morimoto, Water Moderated Th/U-233 Breeder Reactor, Proc. Int. Conf. Specialists’ Meeting on Potential of Small Nuclear Reactors for Future Clean and Safe Energy Source (October 23–25, 1991, Tokyo, Japan), 197, 1991.
[17] S. Permana, N. Takaki, and H. Sekimoto, Impact of Different Moderator Ratios with Light and Heavy Water Cooled Reactors in Equilibrium States, Annals of Nuclear Energy, 33(7), 561-572, 2006.
[18] S. Permana, N. Takaki, and H. Sekimoto, Breeding Capability and Void Reactivity Analysis of Heavy-Water-Cooled Thorium Reactor, Journal of Nuclear Science and Technology, 45(7), 589-600, 2007.
[19] T. Iwamura, T. Okubo, and S. Shimada, Research on Reduced-Moderation Water Reactor (RMWR), JAERI Research/Code 99-058, Japan Atomic Energy Research Institute (JAERI), 1999.
[20] K. Hibi, S. Shimada, T. Okubo, T. Iwamura, and S. Wada, Conceptual Designing of Reduced-moderation Water Reactor with Heavy Water Coolant, Nuclear Engineering and Design, 210(1-3), 9-19, 2001.
[21] K. Hibi and H. Sekimoto, Investigation of Neutron Reaction Behavior in Water-cooled FBR with MOX Fuel, Journal of Nuclear Science and Technology, 42(2), 153-160, 2005.
[22] N. Takaki, Neutronic Potential of Water Cooled Reactor with Actinide Closed Fuel Cycle, Progress in Nuclear Energy, 37(1–4) 223-228, 2000.
[23] N. Takaki, S. Permana, and H. Sekimoto, Actinide Burning Performance of Water-cooled Thorium Breeder, Proc. of Information Exchange Meeting on Actinide and Fission Product Partitioning and Transmutation (October 6-10, 2008, Mito, Japan), 2008.
[24] T. Iwamura, S. Uchikawa, T. Okubo, T. Kugo, H. Akie, Y. Nakano, and T. Nakatsuka, Concept of Innovative Water Reactor for Flexible Fuel Cycle (FLWR), Nuclear Engineering and Design, 236(14-16), 1599-1605, 2006.
[25] S. Uchikawa, T. Okubo, T. Kugo, H. Akie, R. Takeda, Y. Nakano, A. Ohunki, and T. Iwamura, Conceptual Design of Innovative Water Reactor for Flexible Fuel Cycle (FLWR) and its Recycle Characteristics, Journal of Nuclear Science and Technology, 44(3), 277-284, 2007.
[26] H. Takahashi, U. Rohatgi, and T.J. Downar, A Proliferation Resistant Hexagonal Tight Lattice Fueled Core for Increased Burnup and Reduced Fuel Storage Requirements, U. S. DOE Nuclear Energy Research Initiative, 2000.
[27] L. B. Freeman, B. R. Beaudoin, R. A. Frederickson, G. L. Hartfield, H. C. Hecker, S. Milani, W. K. Sarber, and W. C. Schick, Physics Experiments and Lifetime Performance of the Light Water Breeder Reactor, Nuclear Science and Engineering, 102(4), 341-364, 2017.
[28] A.Nuttin, D. Heuer, A. Billebaud, R.Brissot, C. Le Brun, E. Liatard, J. M. Loiseaux, L. Mathieu, O. Meplan, E. Merle-Lucotte, H. Nifenecker, F. Perdu, and S. David, Potential of Thorium Molten Salt Reactors detailed Calculations and Concept Evolution with a View to Large Scale Energy Production, Progress in Nuclear Energy, 46(1), 77-99, 2005.
[29] V. Jagannathan and U. Pal, Towards an Intrinsically Safe and Economic Thorium Breeder Reactor, Energy Conversion and Management, 47(17), 2781-2793, 2006.
[30] IAEA, Thorium Fuel Cycle - Potential Benefits and Challenges, IAEA-TECDOC-1450, IAEA, Vienna, 2005.
[31] N. Trianti, Z. Su’ud, and E. S. Riyana, Design Study of Thorium Cycle Based Long Life Modular Boiling Water Reactors, Indonesian Journal of Physics, 22(4), 133-137, 2016.
[32] N. Trianti, Z. Su’ud, and E. S. Riyana, Design Study of Thorium-232 and Protactinium-231 Based Fuel for Long Life BWR, The 3rd Int. Conf. on Advances in Nuclear Science and Engineering (November 14-17, 2011, Denpasar, Bali), 96-100, 2012.
[33] N. Trianti, Z. Su'ud, I. Arif, and E. S. Riyana, Neutronic Performance of Small Long-Life Boiling Water Reactor Using Thorium as Fuel and the Addition of Protactinium as Burnable Poisons, Advanced Materials Research, 772, 495-500, 2013.
[34] N. Trianti, Z. Su'ud, I. Arif, and E. S. Riyana, Preliminary Design Study of Small Long Life Boiling Water Reactor (BWR) with Tight Lattice Thorium Nitride Fuel, The 4th Int. Conf. on Advances in Nuclear Science and Engineering (September 16-19, 2013, Denpasar, Bali), 80-84, 2014.
[35] N. Trianti, Z. Su'ud, I. Arif, S. Permana, and E. S. Riyana, Power Flattening on Design Study of Small Long-Life Boiling Water Reactor (BWR) with Tight Lattice Thorium Nitride Fuel, Applied Mechanics and Materials, 751, 257- 262, 2015.
[36] N. Trianti, Nurjanah, Z. Su'ud, I. Arif, and S. Permana, Thermalhydraulic Calculation for Boiling Water Reactor and its Natural Circulation Component, The 5th Int. Conf. on Mathematics and Natural Sciences (November 2-3, 2014, Bandung, Indonesia), 120003, 2015.
[37] M. N. Subkhi, Z. Su’ud, A. Waris, and S. Permana, Optimization of Small Long-Life PWR based on Thorium Fuel, The 5th Int. Conf. on Mathematics and Natural Sciences (November 2-3, 2014, Bandung, Indonesia), 120001, 2015.
[38] M. N. Subkhi, Z. Su’ud, A. Waris, and S. Permana, Conceptual Design Study of Small Long-Life PWR based on Thorium Cycle Fuel, The 4th Int. Conf. on Advances in Nuclear Science and Engineering (September 16-19, 2013, Denpasar, Bali), 61-64, 2014.
[39] A. A. Galahom, Simulate the Effect of Integral Burnable Absorber on The Neutronic Characteristics of a PWR Assembly, Nuclear Energy and Technology, 4(4), 287–293, 2018.
[40] Rouf and Z. Su’ud, Analysis of Burnable Poison Effect on Combined (Th-U)O2 Fuel Cycle Performance in 800 MWt Long-life PWR, Indian Journal of Science and Technology, 9(28), 1-8, 2016.
[41] IAEA, Advances in Small Modular Reactor Technology Developments. A Supplement to: IAEA Advanced Reactors Information System (ARIS), 2016 Edition, IAEA, Vienna, 2016.
[42] K. Okumura, T. Kugo, K. Kaneko, and K. Tsuchihashi, SRAC2006: A Comprehensive Neutronics Calculation Code System, Japan Atomic Energy Research Institute (JAERI), 2007.
[2] Yudiarto et al., Indonesia Energy Outlook 2018. Center of Assessment for Process and Energy Industry, Jakarta, 2018.
[3] Sub-Directorate on Investment of Electricity, The Investment Opportunities On Electricity Sector 2017-2021. Directorate General of Electricity, Jakarta, 2016.
[4] M. N. Subkhi, Z. Su’ud, and A. Waris, Netronic Design of Small Long-Life PWR using Thorium Cycle, Advanced Materials Research, 772, 524-529, 2013.
[5] M. N. Subkhi, Z. Su’ud, A. Waris, and S. Permana, Design Concept of Small Long-Life PWR Using Square and Hexagonal Thorium Fuel, ARPN Journal of Engineering and Applied Sciences, 11(2), 830-832, 2016.
[6] T. Takei and A. Yamaji, Core Design of PWR-type Seed-blanket Core Breeder Reactor with Tightly Packed Fuel Assembly, Nuclear Engineering and Design, 333, 45-54, 2018.
[7] C. Juan, Z. Tao, and R. Ke, The Energy-Saving Diagnosis of PWR Nuclear Power Station Based on The Thermo-Economic Analysis Model, 18th Int. Conf. on Nuclear Engineering (May 17-21, 2010, Xi'an, China), 1, 2010.
[8] D. Irwanto and Z. Su’ud, Design Study of Long Life Thorium-based Pressurized Water Reactor (PWR) Using Annular Fuel System and Protactanium as Burnable Poison, Proceedings of Asian Physics Symposium (December 7-8, 2005, Bandung, Indonesia), 307-313, 2006.
[9] M. N. Subkhi, Z. Su’ud, and A. Waris, Design Study of Long-Life PWR using Thorium Cycle, The 3rd Int. Conf. on Advances in Nuclear Science and Engineering (November 14-17, 2011, Denpasar, Bali),101-106, 2012.
[10] Rouf and Z. Su’ud, Conceptual Core Analysis of Long Life PWR Utilizing Thorium-Uranium Fuel Cycle, Journal of Physics: Conference Series, 739(1), 1-7, 2016.
[11] S. Permana, N. Takaki, and H. Sekimoto, Preliminary Study on Feasibility of Large and Small Water Cooled Thorium Breeder Reactor in Equilibrium States, Progress in Nuclear Energy, 50, 320-324, 2008.
[12] T.K. Kim and T.J. Downar, Thorium Fuel Performance in a Tight Pitch Light Water Reactor Lattice, Nuclear Technology, 138(1), 17-29, 2007.
[13] M. Lung and O. Gremm, Perspectives of the Thorium Fuel Cycle, Nuclear Engineering and Design, 180(2), 133-146, 1998.
[14] T. Ünak, What is the Potential Use of Thorium in the Future Energy Production Technology?, Progress in Nuclear Energy, 37(1-4), 137-144, 2000.
[15] S. Permana, N. Takaki, and H. Sekimoto, Feasible Region of Design Parameters for Water Cooled Thorium Breeder Reactor, Journal of Nuclear Science and Technology, 44(7), 946-957, 2007.
[16] H. Akie, Y. Ishiguro, and Y. Morimoto, Water Moderated Th/U-233 Breeder Reactor, Proc. Int. Conf. Specialists’ Meeting on Potential of Small Nuclear Reactors for Future Clean and Safe Energy Source (October 23–25, 1991, Tokyo, Japan), 197, 1991.
[17] S. Permana, N. Takaki, and H. Sekimoto, Impact of Different Moderator Ratios with Light and Heavy Water Cooled Reactors in Equilibrium States, Annals of Nuclear Energy, 33(7), 561-572, 2006.
[18] S. Permana, N. Takaki, and H. Sekimoto, Breeding Capability and Void Reactivity Analysis of Heavy-Water-Cooled Thorium Reactor, Journal of Nuclear Science and Technology, 45(7), 589-600, 2007.
[19] T. Iwamura, T. Okubo, and S. Shimada, Research on Reduced-Moderation Water Reactor (RMWR), JAERI Research/Code 99-058, Japan Atomic Energy Research Institute (JAERI), 1999.
[20] K. Hibi, S. Shimada, T. Okubo, T. Iwamura, and S. Wada, Conceptual Designing of Reduced-moderation Water Reactor with Heavy Water Coolant, Nuclear Engineering and Design, 210(1-3), 9-19, 2001.
[21] K. Hibi and H. Sekimoto, Investigation of Neutron Reaction Behavior in Water-cooled FBR with MOX Fuel, Journal of Nuclear Science and Technology, 42(2), 153-160, 2005.
[22] N. Takaki, Neutronic Potential of Water Cooled Reactor with Actinide Closed Fuel Cycle, Progress in Nuclear Energy, 37(1–4) 223-228, 2000.
[23] N. Takaki, S. Permana, and H. Sekimoto, Actinide Burning Performance of Water-cooled Thorium Breeder, Proc. of Information Exchange Meeting on Actinide and Fission Product Partitioning and Transmutation (October 6-10, 2008, Mito, Japan), 2008.
[24] T. Iwamura, S. Uchikawa, T. Okubo, T. Kugo, H. Akie, Y. Nakano, and T. Nakatsuka, Concept of Innovative Water Reactor for Flexible Fuel Cycle (FLWR), Nuclear Engineering and Design, 236(14-16), 1599-1605, 2006.
[25] S. Uchikawa, T. Okubo, T. Kugo, H. Akie, R. Takeda, Y. Nakano, A. Ohunki, and T. Iwamura, Conceptual Design of Innovative Water Reactor for Flexible Fuel Cycle (FLWR) and its Recycle Characteristics, Journal of Nuclear Science and Technology, 44(3), 277-284, 2007.
[26] H. Takahashi, U. Rohatgi, and T.J. Downar, A Proliferation Resistant Hexagonal Tight Lattice Fueled Core for Increased Burnup and Reduced Fuel Storage Requirements, U. S. DOE Nuclear Energy Research Initiative, 2000.
[27] L. B. Freeman, B. R. Beaudoin, R. A. Frederickson, G. L. Hartfield, H. C. Hecker, S. Milani, W. K. Sarber, and W. C. Schick, Physics Experiments and Lifetime Performance of the Light Water Breeder Reactor, Nuclear Science and Engineering, 102(4), 341-364, 2017.
[28] A.Nuttin, D. Heuer, A. Billebaud, R.Brissot, C. Le Brun, E. Liatard, J. M. Loiseaux, L. Mathieu, O. Meplan, E. Merle-Lucotte, H. Nifenecker, F. Perdu, and S. David, Potential of Thorium Molten Salt Reactors detailed Calculations and Concept Evolution with a View to Large Scale Energy Production, Progress in Nuclear Energy, 46(1), 77-99, 2005.
[29] V. Jagannathan and U. Pal, Towards an Intrinsically Safe and Economic Thorium Breeder Reactor, Energy Conversion and Management, 47(17), 2781-2793, 2006.
[30] IAEA, Thorium Fuel Cycle - Potential Benefits and Challenges, IAEA-TECDOC-1450, IAEA, Vienna, 2005.
[31] N. Trianti, Z. Su’ud, and E. S. Riyana, Design Study of Thorium Cycle Based Long Life Modular Boiling Water Reactors, Indonesian Journal of Physics, 22(4), 133-137, 2016.
[32] N. Trianti, Z. Su’ud, and E. S. Riyana, Design Study of Thorium-232 and Protactinium-231 Based Fuel for Long Life BWR, The 3rd Int. Conf. on Advances in Nuclear Science and Engineering (November 14-17, 2011, Denpasar, Bali), 96-100, 2012.
[33] N. Trianti, Z. Su'ud, I. Arif, and E. S. Riyana, Neutronic Performance of Small Long-Life Boiling Water Reactor Using Thorium as Fuel and the Addition of Protactinium as Burnable Poisons, Advanced Materials Research, 772, 495-500, 2013.
[34] N. Trianti, Z. Su'ud, I. Arif, and E. S. Riyana, Preliminary Design Study of Small Long Life Boiling Water Reactor (BWR) with Tight Lattice Thorium Nitride Fuel, The 4th Int. Conf. on Advances in Nuclear Science and Engineering (September 16-19, 2013, Denpasar, Bali), 80-84, 2014.
[35] N. Trianti, Z. Su'ud, I. Arif, S. Permana, and E. S. Riyana, Power Flattening on Design Study of Small Long-Life Boiling Water Reactor (BWR) with Tight Lattice Thorium Nitride Fuel, Applied Mechanics and Materials, 751, 257- 262, 2015.
[36] N. Trianti, Nurjanah, Z. Su'ud, I. Arif, and S. Permana, Thermalhydraulic Calculation for Boiling Water Reactor and its Natural Circulation Component, The 5th Int. Conf. on Mathematics and Natural Sciences (November 2-3, 2014, Bandung, Indonesia), 120003, 2015.
[37] M. N. Subkhi, Z. Su’ud, A. Waris, and S. Permana, Optimization of Small Long-Life PWR based on Thorium Fuel, The 5th Int. Conf. on Mathematics and Natural Sciences (November 2-3, 2014, Bandung, Indonesia), 120001, 2015.
[38] M. N. Subkhi, Z. Su’ud, A. Waris, and S. Permana, Conceptual Design Study of Small Long-Life PWR based on Thorium Cycle Fuel, The 4th Int. Conf. on Advances in Nuclear Science and Engineering (September 16-19, 2013, Denpasar, Bali), 61-64, 2014.
[39] A. A. Galahom, Simulate the Effect of Integral Burnable Absorber on The Neutronic Characteristics of a PWR Assembly, Nuclear Energy and Technology, 4(4), 287–293, 2018.
[40] Rouf and Z. Su’ud, Analysis of Burnable Poison Effect on Combined (Th-U)O2 Fuel Cycle Performance in 800 MWt Long-life PWR, Indian Journal of Science and Technology, 9(28), 1-8, 2016.
[41] IAEA, Advances in Small Modular Reactor Technology Developments. A Supplement to: IAEA Advanced Reactors Information System (ARIS), 2016 Edition, IAEA, Vienna, 2016.
[42] K. Okumura, T. Kugo, K. Kaneko, and K. Tsuchihashi, SRAC2006: A Comprehensive Neutronics Calculation Code System, Japan Atomic Energy Research Institute (JAERI), 2007.