Light Water Reactor Archives

Three Mile Island, Notorious in Nuclear Power’s Past, May Herald Its Future

The concrete cooling towers that rise from a sliver of land south of Pennsylvania’s capital became symbols nearly a half-century ago of the risks of nuclear energy.

Now, a plan to restart one of the two reactors at Three Mile Island is at the leading edge of efforts to greatly expand the country’s reliance on atomic fission to meet the growing power demands of homes, businesses and data centers.

Three Mile Island, Notorious in Nuclear Power’s Past, May Herald Its Future Read More »

Real-Time Generation Risk Assessment (GRA) Model for Commercial Nuclear Power Plant

Entergy will partner with Oak Ridge National Laboratory (ORNL) to implement real-time Generation Risk Assessment (GRA) modeling to address these issues. ORNL’s unique experience in implementing GRA models combined with the use of their Operational Performance Risk Assessment (OPRA) software will be used to integrate the model with real-time data. Entergy will roll out the model at one of its operating plants an if successful look to expand to other plants in their fleet.

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Assessment of NuScale SMR Steam Heat Augmentation for Chemical Plant Decarbonization

NuScale will partner with Oak Ridge National Laboratory (ORNL) to perform a techno-economic analysis of a NuScale plant with a novel heat augmentation system for application to a commercial scale chemical production facility to help understand the functional requirements for the system and determine best ways to integrate with the facility.

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PIE-Enabled Study of Aqueous Corrosion & Zr Hydriding in Cr-Coated Cladding

The objective of this project is to enhance understanding of aqueous corrosion and hydrogen transport for Zr hydride formation in Cr-coated claddings, as a function of the Cr-coating deposition method (cold spray (CS) or physical vapor deposition (PVD)).

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Post-Irradiation Examination to Quantify Irradiation-Induced Bowing of SiGA® Silicon Carbide Composite Structures

This project will address first-of-a-kind (FOAK) experimental post-irradiation examination (PIE) of irradiation-induced bowing response in SiC-SiC structures.

Post-Irradiation Examination to Quantify Irradiation-Induced Bowing of SiGA® Silicon Carbide Composite Structures Read More »

Dynamic Natural Convection System, Dynac Systems LLC

This Gateway for Accelerated Innovation in Nuclear voucher paired DYNAC Systems with Idaho National Laboratory to evaluate the company’s Dynamic Natural Convection (DNC) system.

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Modeling of Two-Phase Boiling Flow and Critical Heat Flux with the Star-CCM+® and NEK-2P CFD Codes, Framatome Inc.

This project focuses on the development, implementation, and initial validation of the STAR-CCM+® user-defined functionality for the two-fluid two-phase model (2F-2P). The focus will be on modeling two-phase boiling flow in realistic fuel-bundle geometries, including specific spacer geometries.

Modeling of Two-Phase Boiling Flow and Critical Heat Flux with the Star-CCM+® and NEK-2P CFD Codes, Framatome Inc. Read More »

Advanced Nuclear Fuel Pellet Designs, Exelon Nuclear

The objective of this project is to explore a number of advanced heterogenous fuel design concepts to improve the operational, safety, and economic performance of existing power plants.

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Coupled Neutronic and Thermal Hydraulic Analysis of a Natural Circulation Based Small Modular Reactor Using VERA-CS, SMR, LLC

The objective of this project was to analyze reactor core and system behavior in response to anticipated transients and accident scenarios and to use the Virtual Environment for Reactor Applications (VERA) code suite, which employs multi-physics simulation to model feedback behavior in the reactor core.

Coupled Neutronic and Thermal Hydraulic Analysis of a Natural Circulation Based Small Modular Reactor Using VERA-CS, SMR, LLC Read More »

Testing of I&C Sensors and Cables for Small Modular Reactors, Analysis & Measurement Services Corp

The objective of this project was to use the thermal hydraulics laboratory and vacuum test chambers at Oak Ridge National Laboratory (ORNL) for response characterization of resistance temperature detectors and thermal aging of instrumentation and control (I&C) cables in vacuum to generate more useful data for I&C cable derating purposes.

Testing of I&C Sensors and Cables for Small Modular Reactors, Analysis & Measurement Services Corp Read More »