LEU+ loaded APR1400 using accident tolerant fuel cladding for 24-month two-batch fuel management scheme
1
조회
0
다운로드
0
인용
0
참고문헌
키워드
초록
In thiswork, a 24-month two-batch fuel management strategy for the APR1400 using LEU þ has been investigated, where enrichments of 5.9 and 5.2 w/o are utilized in lieu of the conventional 4e5 w/o UO2 fuel. In addition, an Accident Tolerant Fuel (ATF) clad based on the swaging technology is applied to APR1400 fuel assemblies. In this special ATF clad design, both outer and inner SS316 layers protect the conventional zircaloy clad. Erbia (Er2O3) is introduced as a burnable absorber with two-fold goals to lower the critical boron concentration in the long-cycle LEU þ loaded core as well as to handle the LEU þ fuel in the existing front-end fuel facilities without renewing the license. Two types of fuel assemblies with different loading of gadolinia (Gd2O3) are considered to control both the reactivity and the core radial power distribution. The erbia burnable absorber is uniformly admixed with UO2 in all fuel pins except for the gadolinia-bearing ones. In this study, two core designs were devised with different erbia loading, and core performance and safety parameters were evaluated for each case in comparison with a core design without any burnable absorbers. The core analysis was done using the two-step method. First, cross-sections are generated by the SERPENT 2 Monte Carlo code, and the 3-D neutronic analysis is performed with an in-house multi-physics nodal code KANT
Abstract
In thiswork, a 24-month two-batch fuel management strategy for the APR1400 using LEU þ has been investigated, where enrichments of 5.9 and 5.2 w/o are utilized in lieu of the conventional 4e5 w/o UO2 fuel. In addition, an Accident Tolerant Fuel (ATF) clad based on the swaging technology is applied to APR1400 fuel assemblies. In this special ATF clad design, both outer and inner SS316 layers protect the conventional zircaloy clad. Erbia (Er2O3) is introduced as a burnable absorber with two-fold goals to lower the critical boron concentration in the long-cycle LEU þ loaded core as well as to handle the LEU þ fuel in the existing front-end fuel facilities without renewing the license. Two types of fuel assemblies with different loading of gadolinia (Gd2O3) are considered to control both the reactivity and the core radial power distribution. The erbia burnable absorber is uniformly admixed with UO2 in all fuel pins except for the gadolinia-bearing ones. In this study, two core designs were devised with different erbia loading, and core performance and safety parameters were evaluated for each case in comparison with a core design without any burnable absorbers. The core analysis was done using the two-step method. First, cross-sections are generated by the SERPENT 2 Monte Carlo code, and the 3-D neutronic analysis is performed with an in-house multi-physics nodal code KANT
참고문헌 (32)
- A. Lokhov, "Technical and Economic Aspects of Load Following with Nuclear Power Plants, 2" (2011), NEA, OECD
- Fuel Performance Considerations and Data Needs for Burnup above 62 GWd, "MTU", K. J. Geelhood, 2019, PNNL-29368
- Y. Inagaki, "Fuel safety criteria in NEA member countries, compilation of responses received from member countries fuel safety criteria in NEA member countries, compilation of responses received from member countries", J. Nucl. Sci. Technol, 46(7), pp.677~689 (2003)
- Joseph R. Burns, "Reactor and fuel cycle performance of light water reactor fuel with 235U enrichments above 5", Ann. Nucl. Energy, 142, pp.107423~ (2020)
- Design Control Document Tier 2, "KEPCO", ~, pp.APR1400-K-X-FS-14002-NP, R3 (2018)
- IAEA, "Light Water Reactor Fuel Enrichment beyond the Five Per Cent Limit:Perspectives and Challenges" (2020), IAEA
- Liam Carlson, "Implications of HALEU fuel on the design of SMRs and micro-reactors", Nucl. Eng. Des, 389, pp.111648~ (2022)
- Mohammad Alrwashdeh, "Preliminary neutronic analysis of alternative cladding materials for APR-1400 fuel assembly", Nucl. Eng. Des, 384, pp.111486~ (2021)
- S. L. Chen, "Recent studies on potential accident-tolerant fuelcladding systems in light water reactors", Nucl. Sci. Tech, 31(3), pp.1~30 (2020)
- Alfredo Abe, "Revisiting stainless steel as PWR fuel rod cladding after Fukushima Daiichi accident", J. Energy Power Eng, 8, pp.6~ (2014)
- J. Yanez, "An analysis of the hydrogen explosion in the Fukushima-Daiichi accident", Int. J. Hydrogen Energy, 40(25), pp.8261~8280 (2015)
- Yanan He, "Integrating A multilayer deformation model in FRAPTRAN for accident tolerant fuel analysis", Ann. Nucl. Energy, 133, pp.441~454 (2019)
- J. Galloway, "Accident-tolerant-fuel performance analysis of APMT steel clad", UO2 fuel and APMT steel clad, Nucl. Sci. Eng, pp.2016, 182(4)[DOI]
- 도만석, "Physics study for high-performance and very-low-boron APR1400 core with 24-month cycle length", Nuclear Engineering and Technology, 52(5), pp.869~877 (2020), 한국원자력학회[DOI]
- Thermal Conductivity and Electrical Resistivity of Zircaloy-4, "A.D. Feith", General Electric Co, ~, pp.No. GEMP-669 (1966)
- J.W. Kim, "Study of structural stability at high temperature of pseudo-single tube with double layer as an alternative method for accident-tolerant fuel cladding", J. Nucl. Mater, pp.153800~ (2022)
- D. Y. Kim, "Applicability of swaging as an alternative for the fabrication of accident-tolerant fuel cladding", Energies, 13(12), pp.3182~ (2020)
- J. Ko, "Review of manufacturing technologies for coated accident tolerant fuel cladding", J. Nucl. Mater, pp.153562~ (2022)
- COMSOL Multiphysics, "Introduction to COMSOL Multiphysics®, 9", pp.32~ (1998), COMSOL Multiphysics
- MATPRO-Version 11: A Handbook of Materials Properties for Use in the Analysis of Light Water Reactor Fuel Rod Behavior, "Donald L. Hagrman", Idaho National Engineering Lab, ~, pp.No. NUREG (1979), CR-0497
- International Atomic Energy Agency, "Thermophysical Properties Database of Materials for Light Water Reactors and Heavy Water Reactors" (2006), International Atomic Energy Agency
- Charlotta E. Sanders, "Impact of integral burnable absorbers on PWR burnup credit criticality safety analyses", Proc. Of 2001 ANS Embedded Topical Meeting on Practical Implementation of Nuclear Criticality Safety, pp.11~15 (2001)
- Husam Khalefih, "Feasibility Study of a Two-Batch Soluble-Boron-Free APR-1400 Reactor", Transactions of the Korean Nuclear Society Virtual Spring Meeting (2021)
- S. Yamanaka, "Thermal and mechanical properties of (U, Er) O2", J. Nucl. Mater, 389(1), pp.115~118 (2009)
- H. Xiao, "Microstructure and thermophysical properties of Er2O3-doped UO2 ceramic pellets", J. Nucl. Mater, 534, pp.152109~ (2020)
- New UO 2 Fuel Studies, "P. Dehaudt", ~, pp.No. IAEA-TECDOC-1036 (1998)
- K. W. Kang, "The solidus and liquidus temperatures of UO2eGd2O3 and UO2eEr2O3 fuels", Thermochim. Acta, 455(1-2), pp.134~137 (2007)
- J. Leppanen, "The Serpent Monte Carlo code: status, development and applications in 2013", Ann. Nucl. Energy, 82, pp.142~150 (2015)
- 오태석, "Development and validation of multiphysics PWR core simulator KANT", Nuclear Engineering and Technology, 55(6), pp.2230~2245 (2023), 한국원자력학회[DOI]
- Status Report 83- Advanced Power Reactor 1400 MWe (APR1400), "Korea Electric Power Corporation", KEPCO, 2011
- Husam Khalefih, "A study on control algorithm for daily loadfollow operation in the APR1400 reactor", American Nuclear Society Winter Meeting, 127, pp.1145~1148 (2022)
- Husam Khalefih, "A Study on Daily Load-Follow Operation in the APR1400 Reactor Using Manganese-Based Partial Strength Control Element Assembly", Korea Nuclear Society Winter Meeting (2022)