Code scaling, applicability, and uncertainty (CSAU) methodology is a systematic approach proposed by the US Nuclear Regulatory Commission that can be used to identify and quantify overall nuclear reactor uncertainties, and this estimate methods for reactor safety analysis is in lieu of the earlier licensing practice that used deterministic methods with conservative assumptions to address uncertainties. Since the methodology was proposed about two decades ago, it has been widely used for new reactor designs and existing light water reactor power uprates.
References
- Griveau, Alain (Feb 2007). "Modeling and Transient Analysis for the Pebble Bed Advanced High Temperature Reactor (PB-AHTR)" (PDF). University of California at Berkeley. M.S. Project Report UCBTH-07-001.
- Zhao, Haihua (2012). "Use of forward sensitivity analysis method to improve code scaling, applicability, and uncertainty (CSAU) methodology". Nuclear Engineering and Design. 249: 188–196. doi:10.1016/j.nucengdes.2011.09.042. S2CID 110282580. Retrieved 8 November 2013.
External links
- Young, M.Y.; Bajorek, S.M.; Nissley, M.E.; Hochreiter, L.E. (1998). "Application of code scaling applicability and uncertainty methodology to the large break loss of coolant". Nuclear Engineering and Design. 186 (1–2): 39–52. doi:10.1016/S0029-5493(98)00217-9.
- Boyack, B.E.; Catton, I.; Duffey, R.B.; Griffith, P.; Katsma, K.R.; Lellouche, G.S.; Levy, S.; Rohatgi, U.S.; Wilson, G.E.; Wulff, W.; Zuber, N. (1990). "Quantifying reactor safety margins part 1: An overview of the code scaling, applicability, and uncertainty evaluation methodology". Nuclear Engineering and Design. 119: 1–15. doi:10.1016/0029-5493(90)90071-5.
 | This nuclear technology article is a stub. You can help Misplaced Pages by expanding it. |