Data associated with research towards a surrogate machine learning model for the Advanced Gas-cooled Reactor (AGR). This data was generated using the Parmec software package [1] and can be used to tra

NIAID Data Ecosystem90

Computational study of An-O bonding in ThO2 bulk from hybrid density functional theory within an embedded cluster model

化学键分析

核事故模拟

input files, orbital's png files

Mendeley Data40

Data for: Validation of Coupled Fission Matrix - TRACE Methods for Thermal-Hydraulic and Control Feedback on the Penn State Breazeale Reactor

核事故模拟

热工水力学

Fission matrix database used in coupled FM-TRACE simulations

NIAID Data Ecosystem100

Development of A Coupled Neutron Kinetics And Thermal Hydraulics Code With 3-D Two Group Neutron Kinetics Solver and OpenFOAM by Adding Feedback of Coolant Temperature in Calculation of Cross Section Using DRAGON for Pressurized Heavy Water Reactor

核事故模拟

中子动力学-热工水力学耦合

A loosely coupled reactor is subject to local perturbations due to reactivity device movement that affects the neutron kinetics in a local region of the reactor core. Pressurized Heavy Water Reactor (

NIAID Data Ecosystem60

Data for: Hydrodynamic Model of radionuclide dispersion during accident of Bushehr Nuclear Power Plant

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