Code scaling, applicability, and uncertainty
Kod miqyosini belgilash, qo‘llanilishi va noaniqligi (CSAU) metodologiyasi AQSh Nuclear Regulatory Commission tomonidan taklif qilingan tizimli yondashuv bo‘lib, undan umumiy yadro reaktori noaniqliklarini aniqlash va miqdoriy baholash uchun foydalanish mumkin; reaktor xavfsizligi tahlili uchun ushbu baholash usuli noaniqliklarni bartaraf etishda konservativ taxminlarga ega deterministik usullardan foydalangan avvalgi litsenziyalash amaliyotining o‘rnini egallaydi.[1] Metodologiya taxminan yigirma yil avval taklif qilinganidan beri u yangi reaktor loyihalari va mavjud yengil suvli reaktorlar quvvatini oshirish loyihalarida keng qo‘llanib kelmoqda.[2]
Manbalar
- ↑ Griveau, Alain [„Modeling and Transient Analysis for the Pebble Bed Advanced High Temperature Reactor (PB-AHTR)“. University of California at Berkeley (2007-yil fevral).](https://fhr.nuc.berkeley.edu/wp-content/uploads/2014/10/07-001_PB-AHTR_LOFC_Griveau.pdf}})
- ↑ 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. . Qaraldi: 8 November 2013.Code scaling, applicability, and uncertainty]
Tashqi havolalar
- 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. et al. (1990). [[1](https://digital.library.unt.edu/ark:/67531/metadc1183448/) "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. [2](https://digital.library.unt.edu/ark:/67531/metadc1183448/).