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A Framework for Fuel Damage Ratio Calculation in Spent Nuclear Fuel Transportation KCI 등재 SCOPUS
- 언어ENG
- URLhttps://db.koreascholar.com/Article/Detail/440578
pp.25-42
For risk assessment of spent nuclear fuel (SNF) transportation, it is necessary to calculate the damage ratio of SNF rods loaded in the cask. Due to the complexity in the geometry and material properties of SNF, it is impractical to analyze the detailed behavior of every fuel rod and assembly in a single cask model. This study presents a framework for performing cask-level analysis by sequentially simplifying the fuel rods and spent fuel assemblies for fuel damage ratio (FDR) calculation. Using the simplified fuel rod model developed in previous studies, we constructed a CE 16×16 fuel assembly model and presented a methodology to simplify the CE 16×16 assembly model into cuboids. Cask drop analyses were performed to validate the similarity of the detailed CE 16×16 model and the simplified model. Using the proposed simplified models, a procedure for quantifying the bending load and pinch load applied to the fuel rods during the drop impact is presented. The FDR can then be calculated by comparing the quantified loads with their respective failure criteria. Through a case study, the feasibility of the developed framework for systematic and accurate FDR calculation was effectively demonstrated.
2. Development of Simplified SNFAssembly Model
2.1 Detailed Model of CE 16×16 Assembly
2.2 Equivalent Properties of Simplified FuelAssembly Model
2.3 Verification of Applicability of the SimplifiedModel
3. Procedure for Fuel Damage RatioCalculation
3.1 9 m Drop Analysis Model
3.2 Quantification of Impact Loads
4. Results
4.1 Failure due to Bending Loads
4.2 Failure due to Pinch Loads
4.3 Calculation of Fuel Damage Ratio andVerification
5. Discussion and Conclusions
Nomenclature
Conflict of Interest
Acknowledgements
REFERENCES
