과제정보
본 연구는 한국수력원자력(주) 연구과제(No. 2018-TECH-8)로 수행되었음.
참고문헌
- Cinosi et al, "The effective thermal conductivity of crud and heat transfer from crud-coated PWR fuel", Nuclear Engineering and Design, Vol. 241, pp.792-798, 2011. DOI: https://doi.org/10.1016/j.nucengdes.2010.12.015
- Huh et al., "Preliminary study on effect of the crud deposits during LBLOCA condition", Transactions of the Korean Nuclear Society Autumn Meeting, Korea Nuclear Society, PyeongChang, Korea, October 30-31, 2008.
- Lee and Kim, "Crud and oxide layer modeling for safety analysis of a PWR", Transactions of the Korean Nuclear Society Spring Meeting, Korea Nuclear Society, Jeju, Korea, May 12-13, 2016.
- Cinosi, N. and Walker, S.P., "CFD analysis of localized crud effects on the flow of coolant in nuclear rod bundle", Nuclear Engineering and Design, Vol.305, pp.28-38, 2016. https://doi.org/10.1016/j.nucengdes.2015.12.003
- Petrov et al., "Prediction of CRUD deposition on PWR fuel using a state-of-the-art CFD-based multi-physics computational tool", Nuclear Engineering and Design, Vol.229, pp.95-104, 2016. https://doi.org/10.1016/j.nucengdes.2015.10.010
- Isnaini et al., "Prediction of fuel temperature of AP1000 due to the formation of crud and oxide layer," J. Tek. Reaktor. Nukl, Vol.19 No.2, pp.1152-1166, 2018. DOI: http://dx.doi.org/10.17146/tdm.2017.19.2.3521
- Walter et al., "Proof-of-principle of high-fidelity coupled crud deposition and cycle deposition simulation", Annals of Nuclear Energy, Vol.85, pp.1152-1166, 2015. DOI: https://doi.org/10.1016/j.anucene.2015.07.034
- Hu et al., "Considering the thermal resistance of crud in LOCA analysis", Transactions of the American Nuclear Society, American Nuclear Society, America, Vol.101, pp.590-592, 2009.
- Sang-Jun Ha, Chan-Eok Park, Kyung-Doo Kim, and Chang-Hwan Ban, "Development of the space code for nuclear power plants," Nuclear Engineering and Technology, Vol.43, pp.45-62, 2011. DOI: https://doi.org/10.5516/NET.2011.43.1.045
- Korea Hydro & Nuclear Power Co. Ltd., SPACE 3.0 manual Volume 1 theory manual, S06NX08-K-1-TR-36, Rev.0
- Henshaw, J., et al., 2006. "A model of chemistry and thermal hydraulics in PWR fuel crud deposits", Journal of Nuclear Materials, Vol.353, pp.1-11. DOI: https://doi.org/10.1016/j.jnucmat.2005.01.028
- Pan et al, "Wick Boiling Performance in Porous Deposits with Chimneys", AICHE/ANS National Heat Transfer Conference Symposium on Multiphase and Heat Transfer, American Society of Mechanical Engineers, DENVER, COLORADO, United States, August 1985.
- Lee et al., "Thermal resistance effects of crud and oxide layers to the safety analysis", Top Fuel, Prague Czech Republic, September 30 ~ October 4, 2018.
- W. D. Kingery, J. Francl, R. L. Coble, T. Vasilos, J. "Thermal Conductivity: X, Data for Several Pure Oxide Materials Corrected to Zero Porosity", Journal of the American Ceramic Society, Vol.37, pp.107-111, 1954. https://doi.org/10.1111/j.1551-2916.1954.tb20109.x
- "Thermal Expansion, Heat Capacity and Thermal Conductivity of Nickel Ferrite (NiFe2O4)", Journal of the American Ceramic Society, No.5 pp.1559-1565, 2014.
- Gareth S. Parkinson, "Iron oxide surfaces", Surface Science Reports 71, 272-365, 2016.
- W.G. Luscher et. al., "Material Property Correlations: Comparison between FRAPCON-3.4, FRAPTRAN-1.4, and MATPRO", NUREG/ CR-7024, PNNL-19417, 2011.
- B. S. HEMINGWAY, "Thermodynamic properties for bunsenite, NiO, magnetite, Fe3O4, and hematite, Fe2O3, with comments on selected oxygen buffer reactions", American Mineralogist, Vol.75, pp.781-790, 1990.
- A.T. Nelson et. al., "Thermal Expansion, Heat Capacity and Thermal Conductivity of Nickel Ferrite (NiFe2O4)", Journal of the American Ceramic Society, MIT open access article, 2013.
- SCDAP/RELAP5/MOD3.3 Code Manual: MATPRO - A Library of Materials Properties for Light-Water-Reactor Accident Analysis.
- KL.E. Hochreiter, 1986, FLECHT SEASET Program: Final Report, NUREG/CR-4167, EPRI NP-4112, WCAP-10926.
- Carbajo, J., "A Study on the Rewetting Temperature", Nuclear Engineering and Design, Vol.84, pp.21-52, 1985. https://doi.org/10.1016/0029-5493(85)90310-3
- Inayatov, A. Y., "Correlation of Data on Heat Transfer Flow Parallel to Tube Bundles at Relative Tube Pitches of 1.1 < s/d < 1.6." Heat Transfer-Soviet Research. 7. 3. May-June 1975.
- Bhattacharyya, A. ,"Heat transfer and pressure drop with rough surfaces: A literature survey," AE-141, 1964.
- Ki-Yong Choi et al., "Development of a wall-to-fluid heat transfer package for the space code", Nuclear Engineering and Technology, Vol.41, pp.1143-1156, 2009. DOI: https://doi.org/doi.org/10.5516/NET.2009.41.9.1143