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High-Fidelity Light Water Reactor Analysis with the Numerical Nuclear Reactor

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dc.contributor.authorWeber, David P.-
dc.contributor.authorJoo, Han Gyu-
dc.date.accessioned2009-09-07T03:18:36Z-
dc.date.available2009-09-07T03:18:36Z-
dc.date.issued2007-03-01-
dc.identifier.citationNucl. Sci. Eng., 155, 395 (2007)en
dc.identifier.issn0029-5639-
dc.identifier.urihttps://hdl.handle.net/10371/8787-
dc.description.abstractThe Numerical Nuclear Reactor (NNR) was developed to provide a high-fidelity tool for light
water reactor analysis based on first-principles models. High fidelity is accomplished by integrating full
physics, highly refined solution modules for the coupled neutronic and thermal-hydraulic phenomena.
Each solution module employs methods and models that are formulated faithfully to the first principles
governing the physics, real geometry, and constituents. Specifically, the critical analysis elements that are
incorporated in the coupled code capability are a direct whole-core neutron transport solution and an
ultra-fine-mesh computational fluid dynamics / heat transfer solution, each obtained with explicit (subfuel-
pin-cell level) heterogeneous representations of the components of the core. The considerable computational
resources required for such highly refined modeling are addressed by using massively parallel
computers, which together with the coupled codes constitute the NNR. To establish confidence in the NNR
methodology, verification and validation of the solution modules have been performed and are continuing
for both the neutronic module and the thermal-hydraulic module for single-phase and two-phase boiling
conditions under prototypical pressurized water reactor and boiling water reactor conditions. This paper
describes the features of the NNR and validation of each module and provides the results of several
coupled code calculations.
en
dc.description.sponsorshipThis work was supported by the I-NERI program jointly
funded by the Ministry of Science and Technology of Korea
and the DOE. Additional activities related to the BWR version
of the NNR were supported by the DOE.
en
dc.language.isoenen
dc.publisherAmerican Nuclear Societyen
dc.subjectNumerical Nuclear Reactoren
dc.subjectDeCARTen
dc.subjectHigh-Fidelityen
dc.subjectSimulationen
dc.titleHigh-Fidelity Light Water Reactor Analysis with the Numerical Nuclear Reactoren
dc.typeArticleen
dc.contributor.AlternativeAuthor주한규-
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