Advancement of Integral Fast Reactor

Ali Asif, Waleed Raza, Nazim Muhammad, Ali Amir, Abdul Hanan, Hussain Sajid, Chand Kishore, Kumar Vinod Kumar


In this paper, the advancement of the integral fast reactor (IFR) is studied. We proposed the safety passive inherent approach which keeps the IFR operations safe from the maintenance cost. Additionally, it is observed that when failure appears in the reactor then safety passive inherent works efficiently and it turns off the reactor to preserve the safety. Therefore, it is necessary to use the inherent properties of the metallic fuel such as liquid metal, and it should be cooled in a way to substantial developments in the total appearances of the reactor system. Moreover, the key advantages of the IFR concept are narrated briefly with its mechanic position and the future development and research directions.


Integrated fast reactor, Safety passive inherent, Sodium liquid metal, Economics

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. Walters, L.C., Thirty years of fuels and materials information from EBR-II. Journal of Nuclear Materials 270, 1998: p. 39-88.

. Kwi Lim Lee, K.S.H., Jae Jeong, Chi Woong Choi, Taekyeong Jeong, Sang June Ahn, Seung Won Lee, Won Pyo Chang, Seok Hun Kang, and Jaewoon Yoo, A Preliminary Safety Analysis For the Prototype Gen IV Sodium Cooled Fast Reactor. Nuclear Engineering and Technology, 2016: p. 1071-1082.

. Chang, Y.I., The Integral Fast Reactor. Nuclear Technology, 2017. 88(2): p. 129-138.

. Sofu, T., A Review of Inhrent Safety Characteristics of Metal Alloy Sodium-Cooled Fast Reactor Fuel Against Postulated Accidents. Nuclear Engineering and Technology, 2015: p. 227-239.

. Zeyun wu, C.l., Sarah Morgan, Sama Bilbao y Leon, and Matthew Bucknor, A status review on the thermal stratification modeling methods for Sodium-cooled Fast Reactors. Progress in Nuclear Energy, 2020. 125.

. Pope, M.A., et al., Thermal hydraulic challenges of Gas Cooled Fast Reactors with passive safety features. Nuclear Engineering and Design, 2009. 239(5): p. 840-854.

. Idaho, EBR-II Sixteen year of Operation. 1980: Argonne National Laboratory-Weste. p. 1-83.

. A Rineiskii, W.M., A Badulescu, and YI Kim, Liquid Metal Cooled Reactors Experience in Design and Operation. 2007, IAEA: Austria. p. 1-63.

]9]. DL Porter, H.M.C., PG Medvedev, SL Hayes, and MC Teague, Performance of Low Smeared Density Sodium-Cooled Fast Reactor Metal Fuel. Journal of Nuclear Materials, 2015: p. 1-25.

. Takeda, T., et al., Effect of void propagation to sodium void reactivity in transient analyses of fast reactors with sodium-plenum. Annals of Nuclear Energy, 2018. 119: p. 175-179.

. AS Bochkarev, P.A., AS Korsun, and VS Kharitonov, Modeling of Natural Circulation for the Inherent Safety Analysis of Sodium Colled Fast Reactors. Nuclear Engineering and Technology, 2016: p. 294-298.

. JI Xing, D.S., and Yuxiang Wu, HPR1000 Advanced Pressurized Water Reactor with Active and Passive Safety. Engineering, 2016: p. 79-87.

. Petrovic, L.H.B., Development of Methodology for Efficient Fuel Design Evaluation of the Advanced High Temperature Reactor (AHTR). Annals of Nuclear Energy, 2018: p. 646-660.

. F Khoshahval, A.Z., H Minuchehri, and M Sadighi, and A Norouzi, PWR Fuel Management Optimization using Continuous Particle Swarm Intelligence. Annals of Nuclear Energy, 2010: p. 1263-1271.

. Chang, D.C.W.Y.I., The Integral Fast Reactor Concept: Physics of Operation and Safety. Nuclear Science and Engineering, 2017. 100(4): p. 507-524.

. Jaewoon Yoo, J.C., JaeYong Lim, JinSik Cheon, TaeHo Lee, SungKyun Kim, Kwi LimLee, and Hyung Kook Joo, Overall System Description and Safety Characteristics of Prototype Gen IV Sodium Cooled Fast Reactor in Korea. Nuclear Engineering and Technology, 2016: p. 1059-1070.

. Zhang You Peng, W., Janne Gu, Long Yang, Sheng Zhao , Jin Yang li, and Tian ji peng Axial expansion for prompt safety of a small lead-cooled reactor. Annals of Nuclear Energy, 2020. 147.

. Scott Middlemas, Z.H., Vinay Chauhan, WTanner Yorgason, Robert Schley, Amey Khanolkar, Marat Khafizov, and Dvid Hurley, Determining Local Thermal Transport in a Composite Uranium-Nitride Silicide Nuclear Fuel using Square-pluse Transient Thermoreflectance Technique. Journal of Nuclear Materials, 2020: p. 1-11.

. Hartanto, D., et al., Impacts of Burnup-Dependent Swelling of Metallic Fuel on the Performance of a Compact Breed-and-Burn Fast Reactor. Nuclear Engineering and Technology, 2016. 48(2): p. 330-338.

. W Barry Brook, J.B.V.E., Daniel A Meneley, and Thomas A Blees, The Case for a Near-Term Commerical Demonstration of the Interal Fast Reactor. Sustainable Materials and Technologies, 2015: p. 2-6.

. Benito Mignacca, a.G.L., Economics and Finance of Molten Salt Reactors. Progress in Nuclear Energy, 2020: p. 1-12.

. Haihua Zhao, H.Z., Vincent AMousseau, and Per FPeterson, Improving SFR Economics Through Innovation from Thermal Design and Analysis Aspect. Nuclear Engineering and Design, 2009: p. 1042-1055.


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