This research aims to examine the risk in the technology design of fast breeder reactors while the development depends on safety considerations. The project explored the variables, which could affect positively the expected average fuel burn-up, breeding ratio, and decay heat removal. That is accomplished using features such as guard vessels and elevated pipe routing to prevent the cracked state of both core components and fuel cladding interface conditions. So, the cracked region of fuel was detected by thermal-hydraulic analysis. We used ZrFeCr alloys to estimating of the rise in fuel cladding and coolant that can be incorporated in the design ZrFeCr alloys to uniform corrosion in temperature and 10.3 Mpa pressure. Fast creep of the reactor vessel during the coolant heat-up transient is another issue to be considered corrosion resistance of structural material can be achieved by controlling oxygen content in steel alloy. In this trend, S4337 S5140 steels are wide and can be used in future fossil power plants because of their excellent high-temperature strength.
References
[1]
USDOE & GIF (2014) A Technology Roadmap for Generation IV Nuclear Energy Systems. GIF-002-00 (2002) and Technology Roadmap Update for Generation IV Nuclear Energy Systems, Technical Report GIF (2014).
[2]
GIF Risk & Safety Working Group (2008) Basis for Safety Approach for Design & Assessment of Generation IV Nuclear Systems. GIF/RSWG/2007/002.
[3]
Alemberti, A. (2014) Lead-Cooled Fast Reactor (LFR) Risk and Safety Assessment White Paper. GIF RSWG White Paper.
[4]
Alemberti, A., et al. (2020) Lead-Cooled Fast Reactor (LFR) System Safety Assessment. Generation IV International Forum.
[5]
GIF LFR System Steering Committee (2015) Draft System Research Plan for Lead Fast Reactor. https://www.gen-4.org/gif/jcms/c_118389/gif-lfr-ssa-june-2020
[6]
Ishiwatari, Y., Peng, C., Ikejiri, S. and Oka, Y. (2010) Improvement of Feedwater Controller for the Super Fast Reactor. Journal of Nuclear Science and Technology, 47, 1155-1164. https://doi.org/10.1080/18811248.2010.9720982
[7]
Nakatsuka, T., Oka, Y. and Koshizuka, S. (1998) Control of a Fast Reactor Cooled by Supercritical Light Water. Nuclear Technology, 121, 81-92. https://doi.org/10.13182/NT98-A2821
[8]
Toshinsky, G.I., Dedul, A.V., Komlev, O.G., Kondaurov, A.V. and Petrochenko, V.V. (2020) Lead-Bismuth and Lead as Coolants for Fast Reactors. JSC AKME-Engineering, Moscow. JSC SSC RF-IPPE, Obninsk.
[9]
Ali, O., Wyse, M.E., Odeniyi, K.O., et al. (2022) Evaluation of Safety Management System Effectiveness in a Liquefied Natural Gas Company Peace. Petroleum Training Institute, Effurun.
[10]
Hu, R., Zou, L. and Hu, G. (2019) SAM User’s Guide. Argonne National Laboratory, Lemont, ANL/NSE-19/18. https://doi.org/10.2172/1559541
[11]
Zou, L., Nunez, D. and Hu, R. (2020) Development and Validation of SAM Multi-dimensional Flow Model for Thermal Mixing and Stratification Modeling. Argonne National Laboratory, Lemont, ANL-NSE-20/19. https://doi.org/10.2172/1671335
[12]
Hu, G., Hu, R., Kelly, J.M. and Ortensi, J. (2019) Multi-Physics Simulations of Heat Pipe Micro Reactor. Argonne National Laboratory, Lemont, ANL/NSE-19/25. https://doi.org/10.2172/1569948
[13]
Hollrah, B., et al. (2020) Benchmark Simulation of the Natural Convection Shutdown Heat Removal Test Facility Using SAM. Nuclear Technology, 206, 1337-1350. https://doi.org/10.1080/00295450.2020.1745039
[14]
Hu, R. (2019) Three-Dimensional Flow Model Development for Thermal Mixing and Stratification Modeling in Reactor System Transient Analyses. Nuclear Engineering and Design, 345, 209-215. https://doi.org/10.1016/j.nucengdes.2019.02.018
[15]
Hu, R. (2017) A Fully-Implicit High-Order System Thermal-Hydraulics Model for Advanced Non-LWR Safety Analyses. Annals of Nuclear Energy, 101, 174-181. https://doi.org/10.1016/j.anucene.2016.11.004
[16]
Hu, R. (2017) SAM Theory Manual. Argonne National Laboratory, Lemont, ANL/ NE-17/4. https://doi.org/10.2172/1353375
[17]
Hu, R. and Yu, Y. (2016) A Computationally Efficient Method for Full-Core Conjugate Heat Transfer Modeling of Sodium Fast Reactors. Nuclear Engineering and Design, 308, 182-193. https://doi.org/10.1016/j.nucengdes.2016.08.018
[18]
NEI-18-04 (2018, September 28) Risk-Informed Performance-Based Guidance for Non-Light Water Reactor Licensing Basis Development. Nuclear Energy Institute, Draft Report Revision N.
[19]
10 CFR 50 Appendix A (2001, January) General Design Criteria for Nuclear Power Plants. Code of Federal Regulations, Office of the Federal Register.
