Parameter Estimation for Predictive Simulation of Oscillatory Systems with Model Discrepancy**This research was supported in part by the Air Force Office of Scientific Research grant AFOSR FA9550-11-1-0152. It was also supported by the Consortium for Advanced Simulation of Light Water Reactors (http://www.casl.gov), an Energy Innovation Hub, (http://www.energy.gov/hubs) for Modeling and Simulation of Nuclear Reactors under U.S. Department of Energy Contract No. DE-AC05-00OR22725.

The goal of the U.S. Department of Energy (DOE) Accident Tolerant Fuel Program (ATF) for light water reactors (LWR) is to identify alternative fuel system technologies to further enhance the safety of commercial nuclear power plants. An ATF fuel system would endure loss of cooling in the reactor for a considerably longer period of time than the current systems. The General Electric (GE) and Oak Ridge National Laboratory (ORNL) ATF design concept utilizes an iron-chromium-aluminum (FeCrAl) alloy material as fuel rod cladding in combination with uranium dioxide (UO2) fuel pellets currently in use, resulting in a fuel assembly that leverages the performance of existing/current LWR fuel assembly designs and infrastructure with improved accident tolerance. Significant testing was performed in the last three years to characterize FeCrAl alloys for cladding applications, both under normal operation conditions of the reactor and under accident conditions. This article is a state of the art description of the concept.

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Modeling of Spacer Influence on Post-Dryout Heat Transfer in Heated Channels

Volume 2: Thermal Hydraulics ◽

10.1115/icone14-89713 ◽

2006 ◽

Cited By ~ 1

Author(s):

Henryk Anglart

Keyword(s):

Heat Transfer ◽

Heat Transfer Enhancement ◽

Phenomenological Model ◽

Nuclear Reactors ◽

Light Water Reactors ◽

Transfer Enhancement ◽

Light Water ◽

Operational Conditions ◽

Transfer Processes ◽

Water Reactors

Post-dryout heat transfer plays an important role in safe and economical operations of Light Water Reactors (LWR). This type of heat transfer is avoided under normal operational conditions of nuclear reactors; however, it may occur in transient or accidential situations. To estimate the risk of clad damages due to increase of temperature associated with the occurrence of post-dryout, it is necessary to properly model heat transfer processes under such conditions. The influence of various parameters on heat transfer downstream of spacer has been investigated. It is concluded that heat transfer enhancement due to spacers is largely under-predicted for flows with relatively low quality. For such flows the effect of droplets impinging heated walls is significant and must properly be taken into account. The phenomenological model presented in this paper shows a superior accuracy over correlations and presents a potential to capture the phenomenon of rewetting that occurs downstream of spacers.

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Oxidation behaviour of U3Si2: an experimental and first principles investigation

Physical Chemistry Chemical Physics ◽

10.1039/c7cp07154j ◽

2018 ◽

Vol 20 (7) ◽

pp. 4708-4720 ◽

Cited By ~ 10

Author(s):

Ericmoore Jossou ◽

Ubong Eduok ◽

Nelson Y. Dzade ◽

Barbara Szpunar ◽

Jerzy A. Szpunar

Keyword(s):

First Principles ◽

Nuclear Reactors ◽

Oxidation Behaviour ◽

Light Water Reactors ◽

Next Generation ◽

Light Water ◽

Water Reactors ◽

Metallic Systems

Uranium-containing metallic systems such as U3Si2 are potential Accident Tolerant Fuels (ATFs) for Light Water Reactors (LWRs) and the next generation of nuclear reactors.

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