References
- W.N. Association, Nuclear Power in the World Today, 2021. Available: https://www.world-nuclear.org/information-library/current-and-future-generation/nuclear-power-in-the-world-today.aspx.
- The Fukushima Daiichi Accident. Vienna: INTERNATIONAL ATOMIC ENERGY AGENCY, 2015..
- A.A. Galahom, Study of the possibility of using Europium and Pyrex alloy as burnable absorber in PWR, Ann. Nucl. Energy 110 (2017) 1127-1133. https://doi.org/10.1016/j.anucene.2017.08.052
- A. Abdelghafar Galahom, Searching for the optimum number of integral burnable absorber rods used in PWR assembly, Int. J. Nucl. Energy Sci. Technol. 13 (No. 2) (2019).
- Amr Ibrahim, Moustafa Aziz, S.A. El-Fiki, S.U. El-Kameesy, A.A. Galahom, The effect of homogenization on the neutronic parameters and transmutation of GFR-2400 fast reactor fuel assembly, Ann. Nucl. Energy 110 (2017) (2017) 215-221. https://doi.org/10.1016/j.anucene.2017.06.044
- A.A. Galahom, Simulate the effect of integral burnable absorber on the neutronic characteristics of a PWR assembly, Nuclear Energy Tech. 4 (4) (2018) 287-293. https://doi.org/10.3897/nucet.4.30379
- Mohamed Y.M. Mohsen, Mohamed A.E. Abdel-Rahman, Mohamed Saffaa Hassan, A. Abdelghafar Galahom, Searching for the most optimum burnable absorbers (BAs) for AP-1000 from the neutronic, thermal-hydraulic, and solid mechanics points of view, Nucl. Eng. Des. 391 (2022), 111728.
- Amr Ibrahim, Moustafa Aziz, A. Soad, El-Fiki, Ahmed Abdelghafar Galahom, Comparative analysis between homogeneous and heterogeneous models of gas cooled fast reactor core (GFR-2400), Kerntechnik 87 (4) (2022) 385-397. https://doi.org/10.1515/kern-2021-1050
- B. Mahanthesh, B.J. Gireesha, B.C. PrasannaKumara, N.S. Shashikumar, Marangoni convection radiative flow of dusty nanoliquid with exponential space dependent heat source, Nucl. Eng. Technol. 49 (8) (2017/12/01/2017) 1660-1668. https://doi.org/10.1016/j.net.2017.08.015
- Y.M. Mohamed, a Mohsen, A.E. Mohamed, a Abdel-Rahman, A. Abdelghafar Galahom, Integrated analysis of VVER-1000 fuel assembly fueled with accident tolerant fuel (ATF) materials, Ann. Nucl. Energy 159 (2021), 108330.
- A. Abdelghafar Galahom a, Ehab M. Aboelyazidb, S.A. El-Fikib, Moustafa Aziz, Searching for optimal accident tolerant fuel for the VVER-1200 reactor from the neutronic point of view, 2023, Energy Sources, Part A: Recovery, Utilization, and Environmental Effects 45 (NO. 1) (2023) 1405-1423. https://doi.org/10.1080/15567036.2023.2179694
- Mohamed Y.M. Mohsen, Mohamed A.E. Abdel-Rahman, Mohamed Safaa Hassan, A. Abdelghafar Galahom, Investigating the possible advantage of using LM bonded gap instead of helium in Ap-1000 nuclear power reactor, Nucl. Eng. Des. 380 (2021), 111302.
- K.A. Terrani, Y. Yamamoto, Y.S. Kim, Development status of accident-tolerant fuel for LWRs, J. Nucl. Mater. 448 (1-3) (2014) 374-379. https://doi.org/10.1016/j.jnucmat.2013.12.005
- Mohamed Y.M. Mohsen, Mohamed A.E. Abdel-Rahman, A. Abdelghafar Galahom, Untraditional solution for enhancing the performance of U-20 % Zr metallic alloy as an ATF using liquid metal bonded gap, Kerntechnik 87 (6) (2022) 640-650. https://doi.org/10.1515/kern-2022-0065
- A. Abdelghafar Galahom, Mohamed A.E. Abdel-Rahman, Mohamed Y.M. Mohsen, A. Hakamy, Investigation of the possibility of using a uranium-zirconium metal alloy as a fuel for nuclear power plant AP-1000, Nucl. Eng. Des. 406 (2023), 112257.
- A.I. Elazaka, G.V. Tikhomirov, Ahmed Abdelghafar Galahom, Study the neutronic feasibility of using Zr as an energy regulator instead of traditional methods, Int. J. Energy Res. 45 (2021) 10012-10023. https://doi.org/10.1002/er.6494
- A.A. Galahom, Minimization of the fission product waste by using thorium based fuel instead of uranium dioxide, Nucl. Eng. Des. 314 (2017) (2017) 165-172. https://doi.org/10.1016/j.nucengdes.2017.01.024
- A.A. Galahom, I.I. Bashter, M. Aziz, Study the neutronic analysis and burnup for BWR fueled with hydride fuel using MCNPX code, Prog. Nucl. Energy 77 (2014) 65-71. https://doi.org/10.1016/j.pnucene.2014.06.008
- U.E. Humphrey, M.U. Khandaker, Viability of thorium-based nuclear fuel cycle for the next generation nuclear reactor: issues and prospects, Renew. Sustain. Energy Rev. 97 (2018/12/01/2018) 259-275. https://doi.org/10.1016/j.rser.2018.08.019
- T.R. Govindan Kutty, J. Banerjee, K. Arun, Thermophysical properties of thoria-based fuels, in: D. Das, S.R. Bharadwaj (Eds.), Thoria-based Nuclear Fuels: Thermophysical and Thermodynamic Properties, Fabrication, Reprocessing, and Waste Management, Springer London, London, 2013, pp. 11-70.
- A.A. Galahom, Reducing the plutonium stockpile around the world using a new design of VVER-1200 assembly, Ann. Nucl. Energy 119 (2018) 279-286. https://doi.org/10.1016/j.anucene.2018.05.022
- A.A. Galahom, Improvement of the VVER-1200 fuel cycle by introducing thorium with different fissile material in blanket-seed assembly, Nucl. Sci. Eng. 193 (JUNE 2019) 638-651. https://doi.org/10.1080/00295639.2018.1560757
- A.A. Galahom, Investigate the possibility of burning weapon-grade plutonium using a concentric rods BS assembly of VVER-1200, Ann. Nucl. Energy 148 (2020), 107758.
- A.A. Galahom, I.I. Bashter, M. Aziz, Design of an MCNPX model to simulate the performance of BWRs using thorium as fuel and its validation with HELIOS code, Ann. Nucl. Energy 77 (2015) 393-401. https://doi.org/10.1016/j.anucene.2014.11.030
- A. Ibrahim, Moustafa Aziz, S.U. El-Kameesy, S.A. El-Fiki, A.A. Galahom, Analysis of thorium fuel feasibility in large scale gas cooled fast reactor using MCNPX code, Ann. Nucl. Energy 111 (2018) 460-467. https://doi.org/10.1016/j.anucene.2017.07.029
- A.A. Galahom, Iman Mohamad Sharaf, Finding a suitable fuel type for the disposal of the accumulated minor actinides in the spent nuclear fuel in PWR, Prog. Nucl. Energy 136 (2021), 103749.
- A.A. Galahom, A.I. Elazaka b, c, G.V. Tikhomirov, Searching for managing the reactivity and increasing the fuel cycle life in the PWR by an untraditional method, Nucl. Eng. Des. 383 (2021), 111433.
- A.A. Galahom, Examine the possibility of increasing the plutonium incineration rate in the current operating pressurized water reactor, Prog. Nucl. Energy 142 (2021), 104026.
- A.I. Elazaka, , Georgy Valentinovich Tikhomirov, Vladimir Igorevich Savander, Mohamed A.E. Abdel-Rahman, A. Abdelghafar Galahom, Investigation of a new approach for regulating the reactivity and achieving economic feasibility using thorium in a blanket-seed assembly of pressurized water reactors, Int. J. Energy Res. 46 (2022) 6112-6125. https://doi.org/10.1002/er.7551
- A.A. Galahom, Amr Ibrahim, Integrated analysis to investigate the viability of using Thorium-based fuel instead of traditional fuel in CANDU reactor, Nucl. Eng. Des. 398 (2022), 111969.
- M.Y.M. Mohsen, M.A.E. Abdel-Rahman, A.A. Galahom, Ensuring the possibility of using thorium as a fuel in a pressurized water reactor (PWR), Nucl. Sci. Tech. 32 (12) (2021/12/10 2021) 137.
- A.A. Galahom, M.Y.M. Mohsen, N. Amrani, Explore the possible advantages of using thorium-based fuel in a pressurized water reactor (PWR) Part 1: neutronic analysis, Nucl. Eng. Technol. 54 (1) (2022/01/01/2022) 1-10. https://doi.org/10.1016/j.net.2021.07.019
- COMSOL-Multiphysics, COMSOL documentation, Available: https://doc.comsol.com/5.6/docserver/#!/com.comsol.help.comsol/helpdesk/helpdesk.html, 2020.
- S. Mohamed Y, M Mohsen, Abdelfattah Y, Mohamed A. E. Abdel-Rahman "Thermal-hydraulic and solid mechanics safety analysis for VVER-1000 reactor using analytical and CFD approaches," Prog. Nucl. Energy, vol. 130, p. 103568..
- S. Mohamed, Y. M Mohsen, Y. Abdelfattah, Mohamed A.E. Abdel-Rahman, Thermal-hydraulic and solid mechanics safety analysis for VVER-1000 reactor using analytical and CFD approaches, Prog. Nucl. Energy 130 (2020/12/01/2020), 103568.
- M.A.E.A.-R. Mohamed, Y.M. Mohsen, A. Abdelghafar Galahom, Integrated analysis of VVER-1000 fuel assembly fueled with accident tolerant fuel (ATF) materials, Ann. Nucl. Energy 159 (2021/09/01/2021), 108330.
- M.K. Neil Todreas, Nuclear Systems I Thermal Hydraulic Fundamentals, Hemisphere Publishing Corporation, 1990.
- IAEA, Thermophysical Properties of Materials for Nuclear Engineering: A Tutorial and Collection of Data, INTERNATIONAL ATOMIC ENERGY AGENCY, Vienna, 2009.
- M. Cooper, S. Murphy, P. Fossati, M. Rushton, R. Grimes, Thermophysical and anion diffusion properties of (Ux,Th1-x)O2, Proc. Royal Soci. A 470 (2014), 20140427.
- C. Galvin, M. Cooper, M. Rushton, R. Grimes, Thermophysical properties and oxygen transport in (Thx,Pu1- x)O2, Sci. Rep. 6 (2016) 10-31. https://doi.org/10.1038/srep36024
- H. Muta, Y. Murakami, M. Uno, K. Kurosaki, S. Yamanaka, Thermophysical properties of Th 1- x U x O 2 pellets prepared by spark plasma sintering technique, J. Nucl. Sci. Technol. 50 (2013) 181-187. https://doi.org/10.1080/00223131.2013.757468
- M.J. Rahman, B. Szpunar, J. Szpunar, Comparison of thermomechanical properties of (Ux,Th1-x)O2, (Ux,Pu1-x)O2 and (Pux,Th1-x)O2 systems, J. Nucl. Mater. 513 (2018), 10/01.
- J. Harness, J. Matthews, N. Morton, The specific heat of some uranium and thorium carbides between 1.8◦ K and 4.2◦ K, Br. J. Appl. Phys. 15 (963) (2002) 11-20. https://doi.org/10.1088/0508-3443/15/8/313
- J.K. Fink, M.G. Chasanov, L. Leibowitz, Thermophysical Properties of Thorium and Uranium Systems for Use in Reactor Safety Analysis, 1977, 06/01.
- S.S. Parker, S. Newman, A.J. Fallgren, J.T. White, Thermophysical properties of mixtures of thorium and uranium nitride, J. Occup. Med. 73 (11) (2021/11/01 2021) 3564-3575. https://doi.org/10.1007/s11837-021-04844-2
- W.~M. Rohsenow, J.~P. Hartnett, Y. Cho, Y. ~I, Handbook of Heat Transfer, 1997.
- M.J. Fagan, Finite Element Analysis: Theory and Practice, Longman Scientific & Technical, 1992.
- T.J. Chung, Computational Fluid Dynamics, Cambridge University Press, Cambridge, 2002.
- P.I. Muiruri, O.S. Motsamai, R. Ndeda, A comparative study of RANS-based turbulence models for an upscale wind turbine blade, SN Appl. Sci. 1 (3) (2019/02/18 2019) 237.
- M.Y.M. Mohsen, M.A.E. Abdel-Rahman, Neutronics and Both Analytical and Numerical Solutions for the Rod Centered Subchannel Thermal-Hydraulic Model % J Kerntechnik, 86, 2021, pp. 312-320, 4. https://doi.org/10.1515/kern-2020-0040
- M.K. Neil Todreas, Nuclear Systems I Thermal Hydraulic Fundamentals, Hemisphere Publishing Corporation, 1990.
- T.L.D. Bergman, D.P. Incropera, F. avine, S. A, Fundamentals of Heat and Mass Transfer, 2011.
- C.O.T. Galvin, P.A. Burr, M.W.D. Cooper, P.C.M. Fossati, R.W. Grimes, Using molecular dynamics to predict the solidus and liquidus of mixed oxides (Th,U)O2, (Th,Pu)O2 and (Pu,U)O2, J. Nucl. Mater. 534 (2020/06/01/2020), 152127.