Lifetime thermal analysis of the CANDU spent fuel storage canister at the Wolsung site
2
조회
0
다운로드
0
인용
0
참고문헌
키워드
초록
CANDU spent fuels in the Wolsung site have been stored in dry storage systems, such as concrete canisters and modular air-cooled storage system. The primary role of the canister is to ensure the integrity of the fuel during the storage period, which is significantly influenced by temperature. Thus, thermal analysis for the canister’s components, especially for fuel cladding, is essential to demonstrate its safety. The thermal analysis has been conducted mainly for predicting the peak cladding temperature (PCT) since high temperature of the fuel can promote oxidation and cracking. As the expiration of storage license approaches, fuel transfer to final disposal should be prepared. This also requires a thermal analysis to predict minimum cladding temperature (MCT), which is related with brittleness. So, it is crucial to accurately predict both PCT and MCT during entire storage period. The cladding temperature is primarily influenced by decay heat and ambient conditions. The lifetime PCT may occur during summer at the beginning of storage, while the lifetime MCT occurs during winter at the end of storage. In this study, we calculated the PCT and MCT during the entire storage period using a realistic thermal analysis model and, subsequently, conducted their uncertainty analysis.
Abstract
CANDU spent fuels in the Wolsung site have been stored in dry storage systems, such as concrete canisters and modular air-cooled storage system. The primary role of the canister is to ensure the integrity of the fuel during the storage period, which is significantly influenced by temperature. Thus, thermal analysis for the canister’s components, especially for fuel cladding, is essential to demonstrate its safety. The thermal analysis has been conducted mainly for predicting the peak cladding temperature (PCT) since high temperature of the fuel can promote oxidation and cracking. As the expiration of storage license approaches, fuel transfer to final disposal should be prepared. This also requires a thermal analysis to predict minimum cladding temperature (MCT), which is related with brittleness. So, it is crucial to accurately predict both PCT and MCT during entire storage period. The cladding temperature is primarily influenced by decay heat and ambient conditions. The lifetime PCT may occur during summer at the beginning of storage, while the lifetime MCT occurs during winter at the end of storage. In this study, we calculated the PCT and MCT during the entire storage period using a realistic thermal analysis model and, subsequently, conducted their uncertainty analysis.
참고문헌 (39)
- Safety Analysis Report for Wolsong Unit 1 Spent Nuclear Fuel Dry Storage Facilities, "KHNP", Korea Hydro & Nuclear Power Co, Ltd, ~ (2004)
- Project Safety Analysis Report Spent Fuel Dry Storage Wolsung Nuclear Power Plant #1, "KEPCO", ~ (1990)
- USNRC, "Standard Review Plan for Spent Fuel Dry Storage Systems and Facilities", ~ (2017)
- Ductile to brittle transition temperature for high burnup Zircaloy-4 and ZIRLO cladding alloys exposed to simulated drying-storage conditions, "M. C. Billone", USNRC, Argonne National Lab, ~ (2013)
- Thermal Analysis of Wolsung Unit 1 Spent Fuel Interim Storage Canister, "KEPCO", ~ (1992)
- T. G. Lee, "Realistic thermal analysis of the CANDU spent fuel dry storage canister", Nucl. Eng. Technol (2023)[DOI]
- B. E. Boyack, "Quantifying reactor safety margins: application of code scailing, applicability, and uncertainty evaluation methodology to a large break loss of coolant accident", Nucl. Eng. Des, 119, pp.1~15 (1990)[DOI]
- H. Glaeser, "GRS method for uncertainty and sensitivity evaluation of code results and applications", Sci. Technol. Nucl. Install, 2008, pp.1~7 (2008)[DOI]
- J. C. Helton, "Survey of sampling-based methods for uncertainty and sensitivity analysis", Reliab. Eng. Syst. Saf, 91, pp.1175~1209 (2006)[DOI]
- F. D’auria, "Outline of the uncertainty methodology based on accuracy extrapolation", Nucl. Technol, 109, pp.21~38 (1995)[DOI]
- T. H. Andres, "Sampling methods and sensitivity analysis for large parameter sets", J. Stat. Comput. Simul, 57, pp.77~110 (1997)[DOI]
- KINS, "Audit Calculatation for the LOCA Methodology for KSNP", ~ (2006)
- C. Frepoli, "An overview of westinghouse realistic large break LOCA evaluation model", Sci. Technol. Nucl. Install, 2008, pp.1~15 (2008)[DOI]
- F. D’Auria, "Therm.-Hydraul. Water Cool. Nucl. React", pp.905~950 (2017), Elsevier
- J. Stover, "NUREG-2215 - “Standard Review Plan for Spent Fuel Dry Storage Systems and Facilities,”", Draft Report For Comment, ~
- Computational Fluid Dynamics Best Practice Guidelines for Dry Cask Applications, "G. Zigh", Office of Nuclear Regulatory Research, Office of Nuclear Material Safety and Safeguards, ~ (2013)
- T.J. Baker, "FLUENT User’s Guide", ~ (2021)
- A. G. Croff, "A User’s Manual for the ORIGEN2 Computer Code", ORNL, ~ (1980)
- 2011-2023 Gyeongju area weather report, "Korea Meteorological Administration", Korea Meteorological Administration, ~ (2023)
- Standard for Verification and Validation in Computational Fluid Dynamics and Heat Transfer, "ASME", ASME, ~ (2009)
- S. S. Wilks, "Determination of sample sizes for setting tolerance limits", Ann. Math. Stat, 12, pp.91~96 (1941)
- Spent nuclear fuel effective thermal conductivity report, "TRW Environmental Safety Systems, Inc.", ~ (1996)
- AECL, "Storage Basket Heat Transfer Assessment of the MACSTOR", KN-400 Storage Module, 2002
- J. Abrahamson, "FLUENT Theory Duide", ~ (2021)
- K.H. Lee, "Evaluation of Maximum Allowable Temperature inside Basket of Dry Storage Module for CANDU Spent Fuel", ~
- USNRC, "Packing and Transportation of Radioactive Material", ~ (2022)
- F. P. Incropera, "Principles of Heat and Mass Transfer" (2017), Wiley
- S. T. Thynell, "Discrete-Ordinates method in radiative heat transfer", Int. J. Eng. Sci, 36, pp.1651~1675 (1998)[DOI]
- T. -G. Lee, "Preliminary Assessment of Thermal characteristics of CANDU spent fuel dry storage silo facility using CFD code", J. Energy Eng, 32, pp.36~47 (2023)[DOI]
- Uncertainty and sensitivity analysis of a LB-LOCA in ZION nuclear power plant, "F. Reventos", Nuclear Energy Agency, Committee of the Safety of Nuclear Installations, ~ (2009)
- L. J. Siefken, "SCDAP", RELAP5, MATPRO, USNRC, pp.2001, ~
- B.F. Blackwe, "Uncertainty Estimation in the Determination of Thermal Conductivity of 304 Stainless Steel", ~
- K. Kadoya, "Viscosity and thermal conductivity of dry air in the gaseous phase", J. Phys. Chem. Ref. Data, 14, pp.947~970 (1985)[DOI]
- H. Y. Nam, "Experimental study on the emissivity of stainless steel", Proc. Korean Nucl. Soc. Spring Meet (2001)
- R. Wyczolkowski, "Correlations for the thermal conductivity of selected steel grades as a function of temperature in the range of 0–800◦C", Arch. Thermodyn, 43, pp.29~45 (2022)[DOI]
- M. Kurpinska, "Measurements of thermal conductivity of LWC cement composites using simplified laboratory scale method", Materials, 14, pp.1351~ (2021)[DOI]
- M. M. Otha, "The Concrete Canister Program", Whiteshell Nuclear Research Establishment, ~ (1978)
- R. R. Rhinehart, "Applied Engineering Statistics" (2021), CRC Press
- William Navidi, "Statistics for Engineers and Scientists" (2014), McGraw-Hill