Comparison of the neutronic properties of the (Th-233U)O2, (Th-233U)C, and (Th-233U)N fuels in small long-life PWR cores with 300, 400, and 500 MWth of power
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International Atomic Energy Agency. (2021). Energy, electricity and nuclear power estimates for the period up to 2050. Vienna: IAEA. (Reference Data Series no. 1). https://www.iaea.org/publications/15028/energy-electricity-and-nuclear-power-estimates-for-the-period-up-to-2050.International Atomic Energy Agency.(2021)..Vienna:IAEA.(Reference Data Series no. 1).https://www.iaea.org/publications/15028/energy-electricity-and-nuclear-power-estimates-for-the-period-up-to-2050.Search in Google Scholar
Cummins, W E., Matzie, R. (2018). Design evolution of PWRs: Shippingport to generation III +. Prog. Nucl. Energy, 102, 9-37. DOI: 10.1016/j.pnu-cene.2017.08.008.CumminsW E.MatzieR.(2018).Design evolution of PWRs: Shippingport to generation III +.,102,9-37.DOI:10.1016/j.pnu-cene.2017.08.008.Open DOISearch in Google Scholar
Rowinski, M. K., White, T J., Zhao, J. (2015). Small and medium sized reactors (SMR): A review of technology. Renew. Sust. Energy Rev., 44, 643-656. DOI: 10.1016/j.rser.2015.01.006.RowinskiM. K.WhiteT J.ZhaoJ.(2015).Small and medium sized reactors (SMR): A review of technology..,44,643-656.DOI:10.1016/j.rser.2015.01.006.Open DOISearch in Google Scholar
Akbari-Jeyhouni, R., Rezaei Ochbelagh, D., Maiorino, J. R., D’Auria, F., de Stefani, G. L. (2018). The utilization of thorium in small modular reactors-Part I: Neutronic assessment. Ann. Nucl. Energy, 120, 422-430. DOI: 10.1016/j.anucene.2018.06.013.Akbari-JeyhouniR.Rezaei OchbelaghD.MaiorinoJ. R.D’AuriaF.de StefaniG. L.(2018).The utilization of thorium in small modular reactors-Part I: Neutronic assessment.,120,422-430.DOI:10.1016/j.anucene.2018.06.013.Open DOISearch in Google Scholar
Jagannathan, V, Mathur, A., Khan, S. A. (2016). Thorium utilization in existing and advanced reactor types. Int. J. Hydrog. Energy, 41(17), 7094-7102. DOI: 10.1016/j.ijhydene.2015.12.035.JagannathanVMathurA.KhanS. A.(2016).Thorium utilization in existing and advanced reactor types.,41(17),7094-7102.DOI:10.1016/j.ijhydene.2015.12.035.Open DOISearch in Google Scholar
du Toit, M. H., Naicker, V. V. (2018). Neutronic design of homogeneous thorium/uranium fuel for 24 month fuel cycles in the European pressurized reactor using MCNP6. Nucl. Eng. Des., 337 (5), 394-405. DOI: 10.1016/j.nucengdes.2018.07.023.du ToitM. H.NaickerV. V.(2018).Neutronic design of homogeneous thorium/uranium fuel for 24 month fuel cycles in the European pressurized reactor using MCNP6..,337(5),394-405.DOI:10.1016/j.nucengdes.2018.07.023.Open DOISearch in Google Scholar
Tsige-Tamirat, H. (2011). Neutronics assessment of the use of thorium fuels in current pressurized water reactors. Prog. Nucl. Energy, 53 (6), 717-721. DOI: 10.1016/j.pnucene.2011.04.005.Tsige-TamiratH.(2011).Neutronics assessment of the use of thorium fuels in current pressurized water reactors.,53(6),717-721.DOI:10.1016/j.pnucene.2011.04.005.Open DOISearch in Google Scholar
Gorton, J. P., Collins, B. S., Nelson, A. T., Brown, N. R. (2019). Reactor performance and safety characteristics of ThN-UN fuel concepts in a PWR. Nucl. Eng. Des., 355(7), 110317. DOI: 10.1016/j.nuceng-des.2019.110317.GortonJ. P.CollinsB. S.NelsonA. T.BrownN. R.(2019).Reactor performance and safety characteristics of ThN-UN fuel concepts in a PWR..,355(7),110317.DOI:10.1016/j.nuceng-des.2019.110317.Open DOISearch in Google Scholar
Trellue, H. R., Bathke, C. G., Sadasivan, P. (2011). Neutronics and material attractiveness for PWR thorium systems using Monte Carlo techniques. Prog. Nucl. Energy, 53 (6), 698-707. DOI: 10.1016/j. pnucene.2011.04.007.TrellueH. R.BathkeC. G.SadasivanP.(2011).Neutronics and material attractiveness for PWR thorium systems using Monte Carlo techniques.,53(6),698-707.DOI:10.1016/j.pnucene.2011.04.007.Open DOISearch in Google Scholar
Subki, I., Pramutadi, A., Rida, S. N. M., Su’ud, Z., Eka Sapta, R., Nurul, S. Muh., Topan, S., Astuti, Y, Soentono, S. (2008). The utilization of thorium for long-life small thermal reactors without on-site refueling. Prog. Nucl. Energy, 50(2/6), 152-156. DOI: 10.1016/j.pnucene.2007.10.029.SubkiI.PramutadiA.RidaS. N. M.Su’udZ.Eka SaptaR.NurulS. Muh.TopanS.AstutiYSoentonoS.(2008).The utilization of thorium for long-life small thermal reactors without on-site refueling.,50(2/6),152-156.DOI:10.1016/j.pnucene.2007.10.029.Open DOISearch in Google Scholar
Raj, D., Kannan, U. (2022). Analysis for the use of thorium based fuel in LWRs. Ann. Nucl. Energy, 174, 109162. DOI: 10.1016/j.anucene.2022.109162.RajD.KannanU.(2022).Analysis for the use of thorium based fuel in LWRs.,174,109162.DOI:10.1016/j.anucene.2022.109162.Open DOISearch in Google Scholar
Humphrey, U. E., Khandaker, M. U. (2018). Viability of thorium-based nuclear fuel cycle for the next generation nuclear reactor: Issues and prospects. Renew. Sust. Energ. Rev., 97 (8), 259-275. DOI: 10.1016/j.rser.2018.08.019.HumphreyU. E.KhandakerM. U.(2018).Viability of thorium-based nuclear fuel cycle for the next generation nuclear reactor: Issues and prospects..,97(8),259-275.DOI:10.1016/j.rser.2018.08.019.Open DOISearch in Google Scholar
Oettingen, M., Cetnar, J. (2021). Numerical modelling of modular high-temperature gas-cooled reactors with thorium fuel. Nukleonika, 66 (4), 133-138. DOI: 10.2478/nuka-2021-0020.OettingenM.CetnarJ.(2021).Numerical modelling of modular high-temperature gas-cooled reactors with thorium fuel.,66(4),133-138.DOI:10.2478/nuka-2021-0020.Open DOISearch in Google Scholar
Uguru, E. H., Sani, S. F. A., Khandaker, M. U., Rabir, M. H. (2020). Investigation on the effect of238U replacement with232Th in small modular reactor (SMR) fuel matrix. Prog. Nucl. Energy, 118 (2), 103108. DOI: 10.1016/j.pnucene.2019.103108.UguruE. H.SaniS. F. A.KhandakerM. U.RabirM. H.(2020).Investigation on the effect of238U replacement with232Th in small modular reactor (SMR) fuel matrix.,118(2),103108.DOI:10.1016/j.pnucene.2019.103108.Open DOISearch in Google Scholar
Galahom, A. A., Mohsen, M. Y. M., Amrani, N. (2022). Explore the possible advantages of using thorium-based fuel in a pressurized water reactor (PWR). Part 1: Neutronic analysis. Nucl. Eng. Tech-nol., 54(1), 1-10. DOI: 10.1016/j.net.2021.07.019.GalahomA. A.MohsenM. Y. M.AmraniN.(2022).Explore the possible advantages of using thorium-based fuel in a pressurized water reactor (PWR). Part 1: Neutronic analysis..,54(1),1-10.DOI:10.1016/j.net.2021.07.019.Open DOISearch in Google Scholar
Oettingen, M., Skolik, K. (2016). Numerical design of the Seed-Blanket Unit for the thorium nuclear fuel cycle. E3S Web of Conf., 10, 3-7. DOI: 10.1051/ e3sconf/20161000067.OettingenM.SkolikK.(2016).Numerical design of the Seed-Blanket Unit for the thorium nuclear fuel cycle..,10,3-7.DOI:10.1051/e3sconf/20161000067.Open DOISearch in Google Scholar
Liu, R., Cai, J., Zhou, W. (2020). Multiphysics modeling of thorium-based fuel performance with a two-layer SiC cladding in a light water reactor. Ann. Nucl. Energy, 136, 107036. DOI: 10.1016/j. anucene.2019.107036.LiuR.CaiJ.ZhouW.(2020).Multiphysics modeling of thorium-based fuel performance with a two-layer SiC cladding in a light water reactor.,136,107036.DOI:10.1016/j.anucene.2019.107036.Open DOISearch in Google Scholar
Castro, V. F., Velasquez, C. E., Pereira, C. (2020). Criticality and depletion analysis of reprocessed fuel spiked with thorium in a PWR core. Nucl. Eng. Des., 360 (1), 110514. DOI: 10.1016/j.nuceng-des.2020.110514.CastroV. F.VelasquezC. E.PereiraC.(2020).Criticality and depletion analysis of reprocessed fuel spiked with thorium in a PWR core..,360(1),110514.DOI:10.1016/j.nuceng-des.2020.110514.Open DOISearch in Google Scholar
Tucker, L. P., Usman, S. (2018). Thorium-based mixed oxide fuel in a pressurized water reactor: A burnup analysis with MCNP. Ann. Nucl. Energy, 111, 163-175. DOI: 10.1016/j.anucene.2017.08.057.TuckerL. P.UsmanS.(2018).Thorium-based mixed oxide fuel in a pressurized water reactor: A burnup analysis with MCNP.,111,163-175.DOI:10.1016/j.anucene.2017.08.057.Open DOISearch in Google Scholar
Maiorino, J. R., Stefani, G. L., Moreira, J. M. L., Rossi, P C. R., Santos, T A. (2017). Feasibility to convert an advanced PWR from UO2 to a mixed U/ThO2 core-Part I: Parametric studies. Ann. Nucl. Energy, 102, 47-55. DOI: 10.1016/j.anucene.2016.12.010.MaiorinoJ. R.StefaniG. L.MoreiraJ. M. L.RossiP C.R.SantosT A.(2017).Feasibility to convert an advanced PWR from UO2 to a mixed U/ThO2 core-Part I: Parametric studies.,102,47-55.DOI:10.1016/j.anucene.2016.12.010.Open DOISearch in Google Scholar
Zainuddin, N. Z., Parks, G. T, Shwageraus, E. (2016). The factors affecting MTC of thorium-pluto-nium-fuelled PWRs. Ann. Nucl. Energy, 98, 132-143. DOI: 10.1016/j.anucene.2016.07.034.ZainuddinN. Z.ParksG.TShwagerausE.(2016).The factors affecting MTC of thorium-pluto-nium-fuelled PWRs.,98,132-143.DOI:10.1016/j.anucene.2016.07.034.Open DOISearch in Google Scholar
Morrison, S. L., Lindley, B. A., Parks, G. T (2018). Isotopic and spectral effects of Pu quality in Th-Pu fueled PWRs. Ann. Nucl. Energy, 117, 318-332. DOI: 10.1016/j.anucene.2018.03.025.MorrisonS. L.LindleyB. A.ParksG. T(2018).Isotopic and spectral effects of Pu quality in Th-Pu fueled PWRs.,117,318-332.DOI:10.1016/j.anucene.2018.03.025.Open DOISearch in Google Scholar
Li, J., Li, X., Cai, J. (2021). Neutronic characteristics and feasibility analysis of micro-heterogeneous duplex ThO2-UO2 fuel pin in PWR. Nucl. Eng. Des., 382(3), 111382. DOI: 10.1016/j.nuceng-des.2021.111382.LiJ.LiX.CaiJ.(2021).Neutronic characteristics and feasibility analysis of micro-heterogeneous duplex ThO2-UO2 fuel pin in PWR..,382(3),111382.DOI:10.1016/j.nuceng-des.2021.111382.Open DOISearch in Google Scholar
Baldova, D., Fridman, E., Shwageraus, E. (2016). High conversion Th-U233 fuel for current generation of PWRs: Part III-Fuel availability and utilization considerations. Ann. Nucl. Energy, 87, 517-526. DOI: 10.1016/j.anucene.2015.10.006.BaldovaD.FridmanE.ShwagerausE.(2016).High conversion Th-U233 fuel for current generation of PWRs: Part III-Fuel availability and utilization considerations.,87,517-526.DOI:10.1016/j.anucene.2015.10.006.Open DOISearch in Google Scholar
Duan, Z., Yang, H., Satah, Y., Murakami, K., Kano, S., Zhao, Z., Shen, J., Abe, K. (2017). Current status of materials development of nuclear fuel cladding tubes for light water reactors. Nucl. Eng. Des., 316, 131-150. DOI: 10.1016/j.nucengdes.2017.02.031.DuanZ.YangH.SatahY.MurakamiK.KanoS.ZhaoZ.ShenJ.AbeK.(2017).Current status of materials development of nuclear fuel cladding tubes for light water reactors..,316,131-150.DOI:10.1016/j.nucengdes.2017.02.031.Open DOISearch in Google Scholar
ARIS-Technical data. (2023). Vienna: International Atomic Energy Agency. https://aris.iaea.org/sites/ power.html (accessed August 07, 2023)..(2023).Vienna:International Atomic Energy Agency.https://aris.iaea.org/sites/power.html(accessed August 07, 2023).Search in Google Scholar
Lapanporo, B. P, Su’Ud, Z. (2022). Parametric study of thorium fuel utilization on small modular pressurized water reactors (PWR). J. Phys.-Conf. Series, 2243 (1). DOI: 10.1088/1742-6596/2243/1/012062.LapanporoB. PSu’UdZ.(2022).Parametric study of thorium fuel utilization on small modular pressurized water reactors (PWR).,2243(1). DOI:10.1088/1742-6596/2243/1/012062.Open DOISearch in Google Scholar
Okumura, K., Kugo, T., Kaneko, K., Tsuchihashi, K. (2007). SRAC2006: A comprehensive neutronics calculation code system. Japan Atomic Energy Agency. DOI: 10.11484/JAEA-DATA-CODE-2007-004.OkumuraK.KugoT.KanekoK.TsuchihashiK.(2007)..Japan Atomic Energy Agency.DOI:10.11484/JAEA-DATA-CODE-2007-004.Open DOISearch in Google Scholar
Kulikov, G. G., Kulikov, E. G., Shmelev, A. N., Apse, V A. (2017). Protactinium-231-New burnable neutron absorber. Nucl. Energy Technol., 3 (4), 255-259. DOI: 10.1016/j.nucet.2017.10.002.KulikovG. G.KulikovE. G.ShmelevA. N.ApseV A.(2017).Protactinium-231-New burnable neutron absorber..,3(4),255-259.DOI:10.1016/j.nucet.2017.10.002.Open DOISearch in Google Scholar
Bae, I. H., Na, M. G., Lee, Y J., Park, G. C. (2008). Calculation of the power peaking factor in a nuclear reactor using support vector regression models. Ann. Nucl. Energy, 35 (12), 2200-2205. DOI: 10.1016/j. anucene.2008.09.004.BaeI. H.NaM. G.LeeY J.ParkG. C.(2008).Calculation of the power peaking factor in a nuclear reactor using support vector regression models.,35(12),2200-2205.DOI:10.1016/j.anucene.2008.09.004.Open DOISearch in Google Scholar
Mohd Ali, N. S., Hamzah, K., Idris, F., Basri, N. A., Sarkawi, M. S., Sazali, M. A., Rabir, H., Minhat, M. S., Zainal, J. (2022). Power peaking factor prediction using ANFIS method. Nucl. Eng. Technol., 54 (2), 608-616. DOI: 10.1016/j.net.2021.08.011.Mohd AliN. S.HamzahK.IdrisF.BasriN. A.SarkawiM. S.SazaliM. A.RabirH.MinhatM. S.ZainalJ.(2022).Power peaking factor prediction using ANFIS method..,54(2),608-616.DOI:10.1016/j.net.2021.08.011.Open DOISearch in Google Scholar
Kubiński, W., Darnowski, P., Chęć, K. (2021). Optimization of the loading pattern of the PWR core using genetic algorithms and multi-purpose fitness function. Nukleonika, 66 (4), 147-151. DOI: 10.2478/nuka-2021-0022.KubińskiW.DarnowskiP.ChęćK.(2021).Optimization of the loading pattern of the PWR core using genetic algorithms and multi-purpose fitness function.,66(4),147-151.DOI:10.2478/nuka-2021-0022.Open DOISearch in Google Scholar
Ashiq, M., Ilyas, M., Ahmad, S. U. I. (2016). Optimization of PWR design parameters for implementation in SMRs. Ann. Nucl. Energy, 94, 123-128. DOI: 10.1016/j.anucene.2015.12.015.AshiqM.IlyasM.AhmadS. U. I.(2016).Optimization of PWR design parameters for implementation in SMRs.,94,123-128.DOI:10.1016/j.anucene.2015.12.015.Open DOISearch in Google Scholar
Chen, C., Mei, H., He, M., Li, T (2022). Neutronics analysis of a 200 kWe space nuclear reactor with an integrated honeycomb core design. Nucl. Eng. Technol., 54 (12), 4743-4750. DOI: 10.1016/j.net.2022.08.012.ChenC.MeiH.HeM.LiT(2022).Neutronics analysis of a 200 kWe space nuclear reactor with an integrated honeycomb core design..,54(12),4743-4750.DOI:10.1016/j.net.2022.08.012.Open DOISearch in Google Scholar
Tverberg, T, Wiesenack, W (2002). Fission gas release and temperature data from XA0202217 instrumented high burnup LWR fuel. In Technical and economic limits to fuel burnup extension (pp. 7-16). Vienna: International Atomic Energy Agency. (IAEA-TECDOC-1299).TverbergTWiesenackW(2002).Fission gas release and temperature data from XA0202217 instrumented high burnup LWR fuel.In(7-16).Vienna:International Atomic Energy Agency.(IAEA-TECDOC-1299).Search in Google Scholar
Kiuchi, K., Ioka, I., Takizawa, M., Wada, S. (2002). Development of advanced cladding material for burnup extension. In Technical and economic limits to fuel burnup extension (pp. 112-125). Vienna: International Atomic Energy Agency. (IAEA-TECDOC-1299).KiuchiK.IokaI.TakizawaM.WadaS.(2002).Development of advanced cladding material for burnup extension.In(112-125).Vienna:International Atomic Energy Agency.(IAEA-TECDOC-1299).Search in Google Scholar