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K.R. Katsma

Publications -  8
Citations -  404

K.R. Katsma is an academic researcher. The author has contributed to research in topics: Loss-of-coolant accident & Pressurized water reactor. The author has an hindex of 7, co-authored 8 publications receiving 360 citations.

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Quantifying reactor safety margins part 1: An overview of the code scaling, applicability, and uncertainty evaluation methodology

TL;DR: The Code Scaling, Applicability, and Uncertainty (CSAU) as mentioned in this paper evaluation methodology combines a top-down approach to define the dominant phenomena with a bottom-up approach to quantify uncertainty.
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Quantifying reactor safety margins part 3: Assessment and ranging of parameters

TL;DR: In this article, the authors compared results from TRAC-PFl/MOD1 code calculations with measurements from separate effects tests and published experimental data for modeling parameters to determine the uncertainty ranges of code input and modeling parameters which dominate the uncertainty in predicting the peak clad temperature for a postulated Large Break Loss of Coolant Accident (LBLOCA) in a four-loop Westinghouse Pressurized Water Reactor.
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Quantifying reactor safety margins part 2: Characterization of important contributors to uncertainty

TL;DR: In this paper, the authors proposed a methodology to quantify uncertainty called Code Scaling, Applicability and Uncertainty (CSAU), which consists of three primary elements containing 14 steps.
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Quantifying reactor safety margins Part 5: Evaluation of scale-up capabilities of best estimate codes☆

TL;DR: In this article, the authors present the CSAU procedure and rational for evaluating the capability of a best estimate code to scale-up processes from reduced scale test facilities to full scale nuclear power plants, and quantifying the effects of scale distortions and/or a limited data base, on code uncertainty to calculate a safety parameter of interest.
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Quantifying reactor safety margins part 4: Uncertainty evaluation of lbloca analysis based on trac-pf1/mod 1

TL;DR: In this paper, the Nuclear Regulatory Commission (NRC) has issued a revised Emergency Core Cooling System (ECCS) rule allowing the use of best estimate computer codes for safety analysis.