Author:
Karpuk L. A.,Novikov V. V.,Gozman M. I.,Khomyakov O. V.
Publisher
Springer Science and Business Media LLC
Reference20 articles.
1. Uffelen, P., Suzuki, M.: 3.19–oxide fuel performance modeling and simulations. Comprehensive Nucl. Mater, vol. 3, pp. 535–577 (2012)
2. V.P. Deniskin, V.I. Nalivaev, I.I. Fedik et al.: Bench modeling of DB LOCA stages for VVER reactor plants. Atomnaya Energiya [In Russian], 96(4), 247–255 (2004).
3. Terrani, K., Wang, D., Ott, L., Montgomery, R.: The effect of fuel thermal conductivity on the behavior of LWR cores during loss-of-coolant accidents. J. Nucl. Mater. 448, 512–519 (2014)
4. Okada, Y., Sato, D., Ogata, K.: Investigation of chromium coated zirconium alloy behavior as accident tolerant fuel cladding for conventional LWRS. TopFuel, vol. 2021. https://www.euronuclear.org/scientific-resources/conference-proceedings/
5. Nuclear Fuel Behaviour in Loss-of-coolant Accident (LOCA) Conditions, OECD/NEA No. 6846 (2009). https://www.oecd-nea.org/upload/docs/application/pdf/2021-03/csni-r2009-15.pdf