Code scaling, applicability, and uncertainty sahifasining manbasini koʻrish

'''Kod miqyosini belgilash, qo‘llanilishi va noaniqligi''' ('''CSAU''') metodologiyasi AQSh [[Nuclear Regulatory Commission]] tomonidan taklif qilingan tizimli yondashuv bo‘lib, undan umumiy [[nuclear reactor|yadro reaktori]] noaniqliklarini aniqlash va miqdoriy baholash uchun foydalanish mumkin; [[Nuclear safety and security|reaktor xavfsizligi]] tahlili uchun ushbu baholash usuli noaniqliklarni bartaraf etishda konservativ taxminlarga ega [[Deterministic system|deterministik]] usullardan foydalangan avvalgi litsenziyalash amaliyotining o‘rnini egallaydi.<ref>{{cite web |last=Griveau|first=Alain |title=Modeling and Transient Analysis for the Pebble Bed Advanced High Temperature Reactor (PB-AHTR) |website=University of California at Berkeley |id=M.S. Project Report UCBTH-07-001|date=Feb 2007 |url=[https://fhr.nuc.berkeley.edu/wp-content/uploads/2014/10/07-001_PB-AHTR_LOFC_Griveau.pdf}}](https://fhr.nuc.berkeley.edu/wp-content/uploads/2014/10/07-001_PB-AHTR_LOFC_Griveau.pdf}})</ref> Metodologiya taxminan yigirma yil avval taklif qilinganidan beri u yangi reaktor loyihalari va mavjud [[light water reactor|yengil suvli reaktorlar]] quvvatini oshirish loyihalarida keng qo‘llanib kelmoqda.<ref name=zhao>{{cite journal|last=Zhao|first=Haihua|title=Use of forward sensitivity analysis method to improve code scaling, applicability, and uncertainty (CSAU) methodology|url=[https://www.researchgate.net/publication/232372848|journal=Nuclear](https://www.researchgate.net/publication/232372848|journal=Nuclear) Engineering and Design|year=2012 |volume=249 |pages=188–196 |access-date=8 November 2013|doi=10.1016/j.nucengdes.2011.09.042|s2cid=110282580 }}</ref>

== Manbalar ==
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==Tashqi havolalar==

* {{cite journal |doi=10.1016/S0029-5493(98)00217-9|title=Application of code scaling applicability and uncertainty methodology to the large break loss of coolant |year=1998 |last1=Young |first1=M.Y. |last2=Bajorek |first2=S.M. |last3=Nissley |first3=M.E. |last4=Hochreiter |first4=L.E. |journal=Nuclear Engineering and Design |volume=186 |issue=1–2 |pages=39–52 }}
* {{cite journal |doi=10.1016/0029-5493(90)90071-5|title=Quantifying reactor safety margins part 1: An overview of the code scaling, applicability, and uncertainty evaluation methodology |year=1990 |last1=Boyack |first1=B.E. |last2=Catton |first2=I. |last3=Duffey |first3=R.B. |last4=Griffith |first4=P. |last5=Katsma |first5=K.R. |last6=Lellouche |first6=G.S. |last7=Levy |first7=S. |last8=Rohatgi |first8=U.S. |last9=Wilson |first9=G.E. |last10=Wulff |first10=W. |last11=Zuber |first11=N. |journal=Nuclear Engineering and Design |volume=119 |pages=1–15 |url=[https://digital.library.unt.edu/ark:/67531/metadc1183448/](https://digital.library.unt.edu/ark:/67531/metadc1183448/) }}

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