Paolo Balestra
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View article: GCR Methods Area Overview & International Collaborations
GCR Methods Area Overview & International Collaborations Open
Presentation of GCR Methods Area Overview & International Collaborations
View article: Overview on ART-GCR DoE program experiments and software validation efforts
Overview on ART-GCR DoE program experiments and software validation efforts Open
View article: Multiphysics Running-In Simulations for Pebble-Bed Reactors with Griffin
Multiphysics Running-In Simulations for Pebble-Bed Reactors with Griffin Open
View article: Generating Advanced Cross Section Libraries with Reduced-Order Model Techniques for High-Temperature Gas Reactor Pebble-Bed Depletion Calculations
Generating Advanced Cross Section Libraries with Reduced-Order Model Techniques for High-Temperature Gas Reactor Pebble-Bed Depletion Calculations Open
View article: Refinement and demonstration of a coupled BISON-Griffin workflow for designing targeted TRISO transient experiments in TREAT
Refinement and demonstration of a coupled BISON-Griffin workflow for designing targeted TRISO transient experiments in TREAT Open
View article: Parameter Study of the Running-In Process for the Generic Pebble Bed Reactor (Gpbr-200)
Parameter Study of the Running-In Process for the Generic Pebble Bed Reactor (Gpbr-200) Open
View article: pnnl/GeoCLUSTER
pnnl/GeoCLUSTER Open
GeoCLUSTER is a Python-based web application that provides a collection of interactive methods for streamlining the visualization of the technical and economic modeling of closed-loop geothermal systems.
View article: Multi-physics Modeling of Radiative Heat Transfer and Fluid Flow for the Reactor Cavity Cooling System
Multi-physics Modeling of Radiative Heat Transfer and Fluid Flow for the Reactor Cavity Cooling System Open
High-temperature gas-cooled reactors (HTGRs) are notable for their high thermal efficiency and potential for combined heat and power applications. These reactors are particularly appealing due to their advanced passive safety features. HTG…
View article: Generating An Advanced Cross-section Library For HTGR Pebble Bed Depletion Calculations Using Reduced-Order Model Generation Techniques
Generating An Advanced Cross-section Library For HTGR Pebble Bed Depletion Calculations Using Reduced-Order Model Generation Techniques Open
For code development, Advanced Reactor Technologies - Gas Cooled Reactors Program (ART-GCR) rely on a collaboration with the Nuclear Energy Advanced Modeling and Simulation (NEAMS) program, but the cross sections generation and the methodo…
View article: Pre-Test Feasibility Study Of Reactivity Transient Testing On TRISO Fuel In The TREAT Reactor
Pre-Test Feasibility Study Of Reactivity Transient Testing On TRISO Fuel In The TREAT Reactor Open
Uranium oxycarbide (UCO)-bearing tri-structural isotropic (TRISO) particle fuels are expected to be used in numerous US commercial reactor applications within the next decade. In this work, we reviewed historical particle fuel transient ex…
View article: Development and demonstration of a BISON–Griffin modeling framework for the design of targeted TRISO transient experiments in the Transient Reactor Test Facility
Development and demonstration of a BISON–Griffin modeling framework for the design of targeted TRISO transient experiments in the Transient Reactor Test Facility Open
View article: Summary Report of the FY24 DOE Contributions to the GIF VHTR CMVB
Summary Report of the FY24 DOE Contributions to the GIF VHTR CMVB Open
The Generation-IV Forum (GIF) Very-High-Temperature Reactor-Computational Methods Validation and Benchmark (VHTR-CMVB) initiative, involving organizations from Korea Atomic Energy Research Institute (KAERI) (South Korea), Institute of Nucl…
View article: NEA HTTR LOFC Project Test#3 Benchmark Results
NEA HTTR LOFC Project Test#3 Benchmark Results Open
In the second half of FY23, the High Temperature Engineering Test Reactor (HTTR) Loss Of Forced Cooling (LOFC)#3 data for the 9 MW test case with Vessel Cooling System (VCS) off were made available through the Nuclear Energy Agency (NEA) L…
View article: Presentation for IRUG - Pressurizer controllers
Presentation for IRUG - Pressurizer controllers Open
View article: Fine Temperature Grid Continuous Energy Cross Section Generation for Monte Carlo Analysis of Xe-100 Design
Fine Temperature Grid Continuous Energy Cross Section Generation for Monte Carlo Analysis of Xe-100 Design Open
The standard “A Compact ENDF (ACE)” data libraries used by Monte Carlo based reactor physics codes calculations are provided by Los Alamos National Laboratory (LANL) with a temperature interval mostly of 300 K (e.g. 300 K, 600 K, 900 K) fo…
View article: High-Temperature Gas-Cooled Pebble-Bed Reactors Running In And Transient Modeling Capabilities Demonstration
High-Temperature Gas-Cooled Pebble-Bed Reactors Running In And Transient Modeling Capabilities Demonstration Open
This study presents a comprehensive benchmarking and verification effort of several thermal-hydraulic and multiphysics capabilities for high-temperature gas-cooled reactor (HTGR) applications. The first part of this effort focuses on the r…
View article: Enabling targeted TRISO transient analyses using the Transient Reactor Test Facility
Enabling targeted TRISO transient analyses using the Transient Reactor Test Facility Open
View article: Sensitivity analysis, surrogate modeling, and optimization of pebble-bed reactors considering normal and accident conditions
Sensitivity analysis, surrogate modeling, and optimization of pebble-bed reactors considering normal and accident conditions Open
View article: Improving the modeling of near-wall interphase heat transfer in porous media models of Pebble Bed Reactors
Improving the modeling of near-wall interphase heat transfer in porous media models of Pebble Bed Reactors Open
View article: [Presentation] Long time scale Multiphysics simulation of spent nuclear fuel canister in MOOSE
[Presentation] Long time scale Multiphysics simulation of spent nuclear fuel canister in MOOSE Open
Pebble-bed reactors are an important class of advanced reactors under consideration for various applications where their fuel would give a significant advantage in siting and high-quality heat production. However, the disposal of their fue…
View article: Capturing the run-in of a pebble-bed reactor by using thermal feedback and high-fidelity neutronics simulations
Capturing the run-in of a pebble-bed reactor by using thermal feedback and high-fidelity neutronics simulations Open
View article: VALIDATION, VERIFICATION, AND CALIBRATION THROUGH A CAUSAL LENS
VALIDATION, VERIFICATION, AND CALIBRATION THROUGH A CAUSAL LENS Open
This paper presents an alternative method based on causal inference to perform validation, verification, and calibration of simulation models. While classical validation and verification approaches focus on the identification of the associ…
View article: Coupled Multiphysics Seismic Analysis of and MSR core
Coupled Multiphysics Seismic Analysis of and MSR core Open
Earthquakes affect numerous nuclear power plants around the world and safe earthquake design requires that the physics of reactors subjected to earthquakes is well understood. This project attempts to understand the physics of molten salt …
View article: IMPLEMENTATION OF TURBULENCE MODELING FOR THE COUPLED GRIFFIN-PRONGHORN SIMULATION OF THE MOLTEN SALT FAST REACTOR FOR THE VIRTUAL TEST BED
IMPLEMENTATION OF TURBULENCE MODELING FOR THE COUPLED GRIFFIN-PRONGHORN SIMULATION OF THE MOLTEN SALT FAST REACTOR FOR THE VIRTUAL TEST BED Open
In support of the Virtual Test Bed (VTB) repository, the Molten Salt Fast Reactor (MSFR) concept is modeled using MOOSE-based tools, notably Griffin and Pronghorn, employing newly implemented initial turbulence models and standard wall fun…
View article: Multi-Physics Coupled Seismic Safety Analysis of Molten-Salt Reactors
Multi-Physics Coupled Seismic Safety Analysis of Molten-Salt Reactors Open
Pool-type Molten Salt Reactors (MSRs) are a promising advanced nuclear reactor concept relying on passive physical behavior to provide increased safety characteristics. The high heat capacity, high boiling point, unpressurized liquid salt …
View article: Coupled Multiphysics Earthquake Simulation of MSRs
Coupled Multiphysics Earthquake Simulation of MSRs Open
Earthquakes affect numerous nuclear power plants around the world and safe earthquake design requires that the physics of reactors subjected to earthquakes is well understood. This project attempts to understand the physics of molten salt …
View article: Pronghorn Porous Media Model Validation with Pressure Drop Measurements
Pronghorn Porous Media Model Validation with Pressure Drop Measurements Open
The verification and validation (V&V) of Pronghorn is imperative to assert its accuracy when predicting the fluid velocity, temperature, and pressure in high temperature gas-cooled reactors. Pronghorn is a coarse-mesh, intermediate-fidelit…
View article: Modeling of a 1/20th Scaled-down Gas Reactor Using MOOSE-based Application Pronghorn
Modeling of a 1/20th Scaled-down Gas Reactor Using MOOSE-based Application Pronghorn Open
University of Idaho (UI) designed and built a 1/20th scaled-down HTGR system to examine the mixing and venting of helium and reactor cavity air after a loss-of-coolant, also known as LOCA, due to a break in the reactor pressure vessel. Com…
View article: Framework For Performing Time-dependent Pebble Bed Reactor Simulations
Framework For Performing Time-dependent Pebble Bed Reactor Simulations Open
The present work details the creation of a high-fidelity Monte Carlo methodology for analyzing the run-in and subsequent approach to equilibrium for PBRs. The methodology entails a Python module wrapped around Serpent so as to perform neut…
View article: Deployment of Neural-Network-Based Neutron Microscopic Cross Sections in the Griffin Reactor Physics Application
Deployment of Neural-Network-Based Neutron Microscopic Cross Sections in the Griffin Reactor Physics Application Open