Show simple item record

contributor authorHuang, Dongli
contributor authorAbdel-Khalik, Hany S.
date accessioned2022-02-04T22:49:30Z
date available2022-02-04T22:49:30Z
date copyright1/1/2020 12:00:00 AM
date issued2020
identifier issn2332-8983
identifier otherners_006_01_011104.pdf
identifier urihttp://yetl.yabesh.ir/yetl1/handle/yetl/4275510
description abstractUncertainty quantification has been recognized by the community as an essential component of best-estimate reactor analysis simulation because it provides a measure by which the credibility of the simulation can be assessed. In a companion paper, a framework for the propagation of nuclear data uncertainties from the multigroup level through lattice physics and core calculations and ultimately to core responses of interest has been developed. The overarching goal of this framework is to automate the propagation, prioritization, mapping, and reduction of uncertainties for reactor analysis core simulation. This paper employs both heavy and light water reactor systems to exemplify the application of this framework. Specifically, the paper is limited to the propagation of the nuclear data starting with the multigroup cross section covariance matrix and down to core responses, e.g., eigenvalue and power distribution, in steady-state core wide calculations. The goal is to demonstrate how the framework employs reduction techniques to compress the uncertainty space into a very small number of active degrees-of-freedom (DOFs), which renders the overall process computationally feasible for day-to-day engineering evaluations.
publisherThe American Society of Mechanical Engineers (ASME)
titleApplication of Cross Sections Uncertainty Propagation Framework to Light and Heavy Water Reactor Systems
typeJournal Paper
journal volume6
journal issue1
journal titleJournal of Nuclear Engineering and Radiation Science
identifier doi10.1115/1.4045032
journal fristpage011104-1
journal lastpage011104-13
page13
treeJournal of Nuclear Engineering and Radiation Science:;2020:;volume( 006 ):;issue: 001
contenttypeFulltext


Files in this item

Thumbnail

This item appears in the following Collection(s)

Show simple item record