Publications associated with our work & products
2023
Gartner, Mathieu Richier Niels Montanari Nicolas; Sampath, Ramprasad
Can smoothed particle hydrodynamics simulate physically realistic movements of underwater vehicles? Journal Article
In: Advanced Robotics, vol. 37, no. 20, pp. 1283-1300, 2023.
Abstract | Links | BibTeX | Tags:
@article{doi:10.1080/01691864.2023.2263046,
title = {Can smoothed particle hydrodynamics simulate physically realistic movements of underwater vehicles?},
author = {Mathieu Richier Niels Montanari Nicolas Gartner and Ramprasad Sampath},
url = {https://doi.org/10.1080/01691864.2023.2263046},
doi = {10.1080/01691864.2023.2263046},
year = {2023},
date = {2023-01-01},
journal = {Advanced Robotics},
volume = {37},
number = {20},
pages = {1283-1300},
publisher = {Taylor & Francis},
abstract = {This work presents the first results using Smoothed Particle Hydrodynamics (SPH), a mesh-free technique, to simulate underwater vehicle motion with the goal of achieving sufficient physical realism and computation time performance capabilities. The objective is not to get very accurate values for the hydrodynamic parameters, but to show that SPH can simulate hydrodynamic parameters with the same order of magnitude as the reference, in order to allow a realistic control of robots in water. First, spherical objects are simulated to check buoyancy realism, speed limit existence, and hydrodynamic parameters in comparison with reference values. Then, horizontal and vertical movements of a capsule-shape object and a real torpedo-shape underwater robot are compared. The results show that buoyancy is respected, and that spherical objects reach a speed limit in accordance with the laws of physics. In addition, added-mass is simulated with 20 % variation on average with respect to the reference and varies homothetically with respect to the object's size. In contrast, drag forces cannot not be simulated with the same level of realism without reducing the particle size, which makes the simulation last longer. SPH for underwater robotics simulation appears to be promising, and ways of further improvements are being considered.},
keywords = {},
pubstate = {published},
tppubtype = {article}
}
This work presents the first results using Smoothed Particle Hydrodynamics (SPH), a mesh-free technique, to simulate underwater vehicle motion with the goal of achieving sufficient physical realism and computation time performance capabilities. The objective is not to get very accurate values for the hydrodynamic parameters, but to show that SPH can simulate hydrodynamic parameters with the same order of magnitude as the reference, in order to allow a realistic control of robots in water. First, spherical objects are simulated to check buoyancy realism, speed limit existence, and hydrodynamic parameters in comparison with reference values. Then, horizontal and vertical movements of a capsule-shape object and a real torpedo-shape underwater robot are compared. The results show that buoyancy is respected, and that spherical objects reach a speed limit in accordance with the laws of physics. In addition, added-mass is simulated with 20 % variation on average with respect to the reference and varies homothetically with respect to the object's size. In contrast, drag forces cannot not be simulated with the same level of realism without reducing the particle size, which makes the simulation last longer. SPH for underwater robotics simulation appears to be promising, and ways of further improvements are being considered.
Steven, Sampath Ramprasad Christian Robby Prescott
FRI3D Fire Simulation Options and Verification Tasks Technical Report
2023, ((Accessed on 07/10/2024)).
@techreport{INL/RPT-22-70424,
title = {FRI3D Fire Simulation Options and Verification Tasks},
author = {Sampath Ramprasad Christian Robby Prescott Steven},
url = {https://doi.org/10.1080/01691864.2023.2263046},
year = {2023},
date = {2023-01-01},
urldate = {2023-01-01},
howpublished = {urlhttps://lwrs.inl.gov/RiskInformed%20Safety%20Margin%20Characterization/FRI3D_CFAST_FDS.pdf},
note = {(Accessed on 07/10/2024)},
keywords = {},
pubstate = {published},
tppubtype = {techreport}
}
2022
Christian, Ramprasad Sampath Steven Prescott Robby
2022.
Abstract | Links | BibTeX | Tags:
@conference{nokey,
title = {Fire Modelling Automation and Visualization in the Context of Fire Probabilistic Risk Analysis for Nuclear Plants},
author = {Ramprasad Sampath Steven Prescott Robby Christian},
url = {https://www.grs.de/sites/default/files/2023-02/GRS-705.pdf},
year = {2022},
date = {2022-10-19},
urldate = {2022-10-19},
journal = {17th International Seminar on FIRE SAFETY IN NUCLEAR POWER PLANTS AND INSTALLATIONS},
institution = {GRS},
abstract = {Internal fires are a dominant hazard contributing to the overall risk for a given nuclear
power plant (NPP), potentially leading to core damage and/or a release of radioactive
materials into the environment. In this respect, fire probabilistic risk assessment (PRA)
has been developed to support the decision-making of NPP operators and regulators.
However, in practice, conducting a fire PRA has turned into a complex, disjoint, costly,
and time-consuming process requiring the use of many different data, methods, and tools
(plant databases, basic and advanced fire modelling, event tree/fault tree analysis, etc.).
The Fire Risk Investigation in 3D (FRI3D) software was developed as part of the research
for enhanced fire analysis under the Risk-Informed Systems Analysis Pathway of the
Light Water Reactor Sustainability Program. The initial goals of this software had two
parts: (1) to provide industry with a tool to simplify the process for developing and using
detailed fire models and (2) to provide a backend platform for future enhanced fire analysis
research. This paper focuses on the first goal and the methods used to simplify fire
modelling and the benefits from visualization.
Fire models are constructed using various tools and methods. Several analytical methods
are used in conjunction with fire zone models and computational fluid dynamics to
calculate the various scenarios including cable and component failures. While these
methods and tools have been shown to provide adequate results, they are costly to implement
and are disconnected. The FRI3D software combines these tools and methods
into a 3D environment with the ability to model and visualize scenarios rapidly, easily,
and accurately. This integrated approach minimizes the risk of human error and reduces
time by automating many of the tasks, then shows results that provide insights not easily
seen in traditional processes.
The use of FRI3D by NPP operators, regulators and engineering consultancy firms is
expected to lead to enhanced fire PRA, increased safety, efficient and expedient regulatory
review, and reduced operating costs.},
keywords = {},
pubstate = {published},
tppubtype = {conference}
}
Internal fires are a dominant hazard contributing to the overall risk for a given nuclear
power plant (NPP), potentially leading to core damage and/or a release of radioactive
materials into the environment. In this respect, fire probabilistic risk assessment (PRA)
has been developed to support the decision-making of NPP operators and regulators.
However, in practice, conducting a fire PRA has turned into a complex, disjoint, costly,
and time-consuming process requiring the use of many different data, methods, and tools
(plant databases, basic and advanced fire modelling, event tree/fault tree analysis, etc.).
The Fire Risk Investigation in 3D (FRI3D) software was developed as part of the research
for enhanced fire analysis under the Risk-Informed Systems Analysis Pathway of the
Light Water Reactor Sustainability Program. The initial goals of this software had two
parts: (1) to provide industry with a tool to simplify the process for developing and using
detailed fire models and (2) to provide a backend platform for future enhanced fire analysis
research. This paper focuses on the first goal and the methods used to simplify fire
modelling and the benefits from visualization.
Fire models are constructed using various tools and methods. Several analytical methods
are used in conjunction with fire zone models and computational fluid dynamics to
calculate the various scenarios including cable and component failures. While these
methods and tools have been shown to provide adequate results, they are costly to implement
and are disconnected. The FRI3D software combines these tools and methods
into a 3D environment with the ability to model and visualize scenarios rapidly, easily,
and accurately. This integrated approach minimizes the risk of human error and reduces
time by automating many of the tasks, then shows results that provide insights not easily
seen in traditional processes.
The use of FRI3D by NPP operators, regulators and engineering consultancy firms is
expected to lead to enhanced fire PRA, increased safety, efficient and expedient regulatory
review, and reduced operating costs.
power plant (NPP), potentially leading to core damage and/or a release of radioactive
materials into the environment. In this respect, fire probabilistic risk assessment (PRA)
has been developed to support the decision-making of NPP operators and regulators.
However, in practice, conducting a fire PRA has turned into a complex, disjoint, costly,
and time-consuming process requiring the use of many different data, methods, and tools
(plant databases, basic and advanced fire modelling, event tree/fault tree analysis, etc.).
The Fire Risk Investigation in 3D (FRI3D) software was developed as part of the research
for enhanced fire analysis under the Risk-Informed Systems Analysis Pathway of the
Light Water Reactor Sustainability Program. The initial goals of this software had two
parts: (1) to provide industry with a tool to simplify the process for developing and using
detailed fire models and (2) to provide a backend platform for future enhanced fire analysis
research. This paper focuses on the first goal and the methods used to simplify fire
modelling and the benefits from visualization.
Fire models are constructed using various tools and methods. Several analytical methods
are used in conjunction with fire zone models and computational fluid dynamics to
calculate the various scenarios including cable and component failures. While these
methods and tools have been shown to provide adequate results, they are costly to implement
and are disconnected. The FRI3D software combines these tools and methods
into a 3D environment with the ability to model and visualize scenarios rapidly, easily,
and accurately. This integrated approach minimizes the risk of human error and reduces
time by automating many of the tasks, then shows results that provide insights not easily
seen in traditional processes.
The use of FRI3D by NPP operators, regulators and engineering consultancy firms is
expected to lead to enhanced fire PRA, increased safety, efficient and expedient regulatory
review, and reduced operating costs.
Prescott, Steven; Knudsen, James; Wood, Stephen Ted
Automated Fire PRA Scenario Modeling in SAPHIRE Using FRI3D Proceedings Article
In: Proceedings of the Probablistic Safety Assesment and Management (PSAM), 2022.
@inproceedings{psam2022,
title = {Automated Fire PRA Scenario Modeling in SAPHIRE Using FRI3D},
author = {Steven Prescott and James Knudsen and Stephen Ted Wood},
url = {https://www.iapsam.org/PSAM16/papers/ST94-PSAM16.pdf},
year = {2022},
date = {2022-01-01},
booktitle = {Proceedings of the Probablistic Safety Assesment and Management (PSAM)},
keywords = {},
pubstate = {published},
tppubtype = {inproceedings}
}
Sampath, Ramprasad
Fire Modeling & Probabilistic Risk Analysis with FRI3D Proceedings Article
In: Proceedings of the Probablistic Safety Assesment and Management (PSAM), 2022.
@inproceedings{psam2022b,
title = {Fire Modeling & Probabilistic Risk Analysis with FRI3D},
author = {Ramprasad Sampath},
url = {https://www.iapsam.org/PSAM16/paper.php?ID=RA340},
year = {2022},
date = {2022-01-01},
urldate = {2022-01-01},
booktitle = {Proceedings of the Probablistic Safety Assesment and Management (PSAM)},
keywords = {},
pubstate = {published},
tppubtype = {inproceedings}
}
2021
Prescott, Steven; Sampath, Ram; Christian, Robby; Vedros, Kurt; Lawrence, Svetlana
Industry Level Integrated Fire Modeling Using Fire Risk Investigation in 3D (FRI3D) Technical Report
2021.
Abstract | Links | BibTeX | Tags:
@techreport{osti_1818298,
title = {Industry Level Integrated Fire Modeling Using Fire Risk Investigation in 3D (FRI3D)},
author = {Steven Prescott and Ram Sampath and Robby Christian and Kurt Vedros and Svetlana Lawrence},
url = {https://www.osti.gov/biblio/1818298},
doi = {10.2172/1818298},
year = {2021},
date = {2021-08-01},
urldate = {2021-08-01},
abstract = {The software Fire Risk Investigation in 3D (FRI3D) has been developed over the last 2 years to integrate 3D spatial modeling with existing fire probabilistic risk assessment (PRA) models and fire simulation codes. The goal of this research and development is to automate many of the fire analysis manual tasks to reduce industry efforts in the initial fire modeling and operational costs for the model maintenance and evaluations required during normal plant operations. The tasks for Fiscal Year (FY) 2021 include first testing the FRI3D modeling capabilities by importing an industry fire model into FRI3D and making a 3D model of a complex/high-risk significant area. (For this work, the switchgear room was chosen.) Then, the second task of FY 2021 is to develop a dynamic fire PRA process that can help optimize traditional fire PRA models. The switchgear room model will be used for the dynamic fire PRA work. This report describes the work and insights learned when using FRI3D software to model both a Nuclear Regulatory Report (NUREG) example models and a full industry switchgear room.
},
keywords = {},
pubstate = {published},
tppubtype = {techreport}
}
The software Fire Risk Investigation in 3D (FRI3D) has been developed over the last 2 years to integrate 3D spatial modeling with existing fire probabilistic risk assessment (PRA) models and fire simulation codes. The goal of this research and development is to automate many of the fire analysis manual tasks to reduce industry efforts in the initial fire modeling and operational costs for the model maintenance and evaluations required during normal plant operations. The tasks for Fiscal Year (FY) 2021 include first testing the FRI3D modeling capabilities by importing an industry fire model into FRI3D and making a 3D model of a complex/high-risk significant area. (For this work, the switchgear room was chosen.) Then, the second task of FY 2021 is to develop a dynamic fire PRA process that can help optimize traditional fire PRA models. The switchgear room model will be used for the dynamic fire PRA work. This report describes the work and insights learned when using FRI3D software to model both a Nuclear Regulatory Report (NUREG) example models and a full industry switchgear room.
Sampath, Ramprasad
An Advanced Simulation based 3D Framework and Toolkit for Fire Protection and Fire Probabilistic Risk Analysis Journal Article
In: 2021.
@article{osti_1820233b,
title = {An Advanced Simulation based 3D Framework and Toolkit for Fire Protection and Fire Probabilistic Risk Analysis},
author = {Ramprasad Sampath},
url = {https://www.osti.gov/biblio/1820233},
year = {2021},
date = {2021-06-01},
keywords = {},
pubstate = {published},
tppubtype = {article}
}
Dinh, Nam
Development and Application of a Data-Driven Methodology for Validation of Risk-Informed Safety Margin Characterization Models Journal Article
In: 2021.
Links | BibTeX | Tags: Neutrino, Validation
@article{osti_1776813b,
title = {Development and Application of a Data-Driven Methodology for Validation of Risk-Informed Safety Margin Characterization Models},
author = {Nam Dinh},
url = {https://www.osti.gov/biblio/1776813},
doi = {10.2172/1776813},
year = {2021},
date = {2021-01-01},
urldate = {2021-01-01},
keywords = {Neutrino, Validation},
pubstate = {published},
tppubtype = {article}
}
Prescott, Steven; Christian, Robby; Biersdorf, John M.; Vedros, Kurt; Sampath, Ram
Visualization and Automation of Fire Modeling Using Fire Risk Investigation in 3D (FRI3D) Conference
2021, (2021 International Topical Meeting on Probabilistic Safety Assessment and Analysis ; Conference date: 07-11-2021 Through 12-11-2021).
BibTeX | Tags:
@conference{f9e385f8da3844f7abaa23b60684fcb6,
title = {Visualization and Automation of Fire Modeling Using Fire Risk Investigation in 3D (FRI3D)},
author = {Steven Prescott and Robby Christian and John M. Biersdorf and Kurt Vedros and Ram Sampath},
year = {2021},
date = {2021-01-01},
note = {2021 International Topical Meeting on Probabilistic Safety Assessment and Analysis ; Conference date: 07-11-2021 Through 12-11-2021},
keywords = {},
pubstate = {published},
tppubtype = {conference}
}
2020
Ryan, Emerald D.; Pope, Chad L.
Coupling of the Smoothed Particle Hydrodynamic Code Neutrino and the Risk Analysis Virtual Environment for Particle Spacing Optimization Journal Article
In: Nuclear Technology, vol. 206, no. 10, pp. 1506-1516, 2020.
Abstract | Links | BibTeX | Tags: Neutrino, SPH
@article{doi:10.1080/00295450.2019.1704576,
title = {Coupling of the Smoothed Particle Hydrodynamic Code Neutrino and the Risk Analysis Virtual Environment for Particle Spacing Optimization},
author = {Emerald D. Ryan and Chad L. Pope},
url = {https://doi.org/10.1080/00295450.2019.1704576},
doi = {10.1080/00295450.2019.1704576},
year = {2020},
date = {2020-02-27},
urldate = {2020-02-27},
journal = {Nuclear Technology},
volume = {206},
number = {10},
pages = {1506-1516},
publisher = {Taylor & Francis},
abstract = {AbstractFlooding is a hazard for nuclear power plants (NPPs) and has caused extensive damage and economic impact. Improved NPP flooding risk characterization starts with improving scenario realism by using physics-based flooding simulations. Smoothed particle hydrodynamics (SPH) is one method for modeling fluid flow and is being investigated for NPP flooding simulation. While still in its infancy as a fluid simulation tool, SPH offers enticing features especially in three-dimensional modeling. However, when conducting SPH simulations, users must establish, inter alia, the appropriate particle spacing, which can be a tedious and time-consuming process. This paper describes the coupling of the SPH code Neutrino and the Idaho National Laboratory developed Risk Analysis Virtual Environment (RAVEN). By coupling Neutrino and RAVEN, the RAVEN optimization capabilities can now be applied to the particle spacing selection problem. A brief description of SPH, the overall capabilities of RAVEN, and the protocol used to couple the codes are provided. Additionally, the paper details a hypothetical problem and demonstrates the ability of automating the particle spacing selection and performing an example particle spacing optimization using RAVEN. With the Neutrino/RAVEN coupling established, a wide range of capabilities can now be utilized including optimization, reduced order model training and analysis, uncertainty quantification, sensitivity analysis, etc. Previously, these capabilities would require extensive work and time from the Neutrino user. Now, these capabilities are readily available and require only the creation of a RAVEN input file.},
keywords = {Neutrino, SPH},
pubstate = {published},
tppubtype = {article}
}
AbstractFlooding is a hazard for nuclear power plants (NPPs) and has caused extensive damage and economic impact. Improved NPP flooding risk characterization starts with improving scenario realism by using physics-based flooding simulations. Smoothed particle hydrodynamics (SPH) is one method for modeling fluid flow and is being investigated for NPP flooding simulation. While still in its infancy as a fluid simulation tool, SPH offers enticing features especially in three-dimensional modeling. However, when conducting SPH simulations, users must establish, inter alia, the appropriate particle spacing, which can be a tedious and time-consuming process. This paper describes the coupling of the SPH code Neutrino and the Idaho National Laboratory developed Risk Analysis Virtual Environment (RAVEN). By coupling Neutrino and RAVEN, the RAVEN optimization capabilities can now be applied to the particle spacing selection problem. A brief description of SPH, the overall capabilities of RAVEN, and the protocol used to couple the codes are provided. Additionally, the paper details a hypothetical problem and demonstrates the ability of automating the particle spacing selection and performing an example particle spacing optimization using RAVEN. With the Neutrino/RAVEN coupling established, a wide range of capabilities can now be utilized including optimization, reduced order model training and analysis, uncertainty quantification, sensitivity analysis, etc. Previously, these capabilities would require extensive work and time from the Neutrino user. Now, these capabilities are readily available and require only the creation of a RAVEN input file.
Gartner, Nicolas
Identification de param`etres hydrodynamiques par simulation avec Smoothed Particle Hydrodynamics PhD Thesis
Université de Toulon, 2020.
Links | BibTeX | Tags: Neutrino
@phdthesis{gartner:tel-03155087,
title = {Identification de param`etres hydrodynamiques par simulation avec Smoothed Particle Hydrodynamics},
author = {Nicolas Gartner},
url = {https://hal.archives-ouvertes.fr/tel-03155087},
year = {2020},
date = {2020-01-01},
number = {2020TOUL0004},
school = {Université de Toulon},
keywords = {Neutrino},
pubstate = {published},
tppubtype = {phdthesis}
}
Lin, Linyu; Montanari, Niels; Prescott, Steven; Sampath, Ram; Bao, Han; Dinh, Nam
Adequacy evaluation of smoothed particle hydrodynamics methods for simulating the external-flooding scenario Journal Article
In: Nuclear Engineering and Design, vol. 365, no. C, pp. 110720, 2020, ISSN: 0029-5493.
Abstract | Links | BibTeX | Tags: CSAU/EMDAP, External flooding, Neutrino, Scaling, SPH, Validation
@article{LIN2020110720b,
title = {Adequacy evaluation of smoothed particle hydrodynamics methods for simulating the external-flooding scenario},
author = {Linyu Lin and Niels Montanari and Steven Prescott and Ram Sampath and Han Bao and Nam Dinh},
url = {https://www.osti.gov/biblio/1633490},
doi = {10.1016/j.nucengdes.2020.110720},
issn = {0029-5493},
year = {2020},
date = {2020-01-01},
urldate = {2020-01-01},
journal = {Nuclear Engineering and Design},
volume = {365},
number = {C},
pages = {110720},
abstract = {In modern nuclear risk analysis for external-flooding scenarios, Computational Fluid Dynamics (CFD) tools are used to simulate the generation, propagation, and interactions of Nuclear Power Plants (NPPs) with the nuclear Systems, Structures, and Components (SSCs). Smoothed Particle Hydrodynamics (SPH), as a Lagrangian and mesh-free method, is one of the particle-based CFD methods. Since SPH methods can effectively handling large-scale fluid simulations with complex interfacial structures, SPH-based software has been used to simulate the impacts of external flood onto nuclear facilities, and the simulation results have been used to support nuclear safety analysis. However, previous risk analysis assumes that SPH methods and the corresponding simulation packages are applicable to the external-hazards risk analysis, and their simulation uncertainties do not affect the confidence of safety decision. Considering the high consequences to nuclear safety induced by simulation errors, a systematic and complete validation process is needed to evaluate the adequacy of SPH simulations in informing related safety decisions. In this study, a scoping-stage assessment is performed for SPH’s adequacy in simulating the real-scale external flooding scenarios, especially in predicting the surface-wave impacts on SSCs at NPP sites. To ensure the completeness and consistency, validation frameworks, Code Scalability Applicability and Uncertainty (CSAU), and its regulatory guide, Evaluation Model Development and Assessment Process (EMDAP) are followed to guide validation activities and to make final code adequacy assessment. First, an external-flooding scenario is designed, and SPH simulations are performed with an SPH-based software named Neutrino. A Phenomenon Identification and Ranking Table (PIRT) is created, and the surface-wave impacts are identified as one of the high-rank phenomena. At the same time, a performance measurement standard is created for measuring the code adequacy in informing safety decisions consistently and transparently. Next, numerical benchmarks are designed for assessing the code adequacy of SPH methods and corresponding software implementations on Neutrino. Next, code accuracy is evaluated by comparing simulation results from Neutrino against experimental measurements in each benchmark. Meanwhile, a scaling analysis is performed to determine a group of dimensionless number for characterizing important physics and to assess the applicability of validation database collected in reduced-scale facility to the prototypic scenario. Finally, results from all activities are brought together to make an adequacy decision. It is found that, based on the current evidence, SPH methods and associated Neutrino software can predict the unbroken surface-wave peak pressure onto stationary rigid with reasonable accuracy if the suggested sizes of particles are used. However, it is suggested by independent reviews that the validity of major assumptions in target applications need to be evaluated with large-scale experiments, and the relevancy of other phenomena like turbulence and air pockets need to be identified with more benchmarks. As for the SPH’s adequacy in predicting the impact forces on dynamic rigid, the available evidence is not sufficient to support the decisions.},
keywords = {CSAU/EMDAP, External flooding, Neutrino, Scaling, SPH, Validation},
pubstate = {published},
tppubtype = {article}
}
In modern nuclear risk analysis for external-flooding scenarios, Computational Fluid Dynamics (CFD) tools are used to simulate the generation, propagation, and interactions of Nuclear Power Plants (NPPs) with the nuclear Systems, Structures, and Components (SSCs). Smoothed Particle Hydrodynamics (SPH), as a Lagrangian and mesh-free method, is one of the particle-based CFD methods. Since SPH methods can effectively handling large-scale fluid simulations with complex interfacial structures, SPH-based software has been used to simulate the impacts of external flood onto nuclear facilities, and the simulation results have been used to support nuclear safety analysis. However, previous risk analysis assumes that SPH methods and the corresponding simulation packages are applicable to the external-hazards risk analysis, and their simulation uncertainties do not affect the confidence of safety decision. Considering the high consequences to nuclear safety induced by simulation errors, a systematic and complete validation process is needed to evaluate the adequacy of SPH simulations in informing related safety decisions. In this study, a scoping-stage assessment is performed for SPH’s adequacy in simulating the real-scale external flooding scenarios, especially in predicting the surface-wave impacts on SSCs at NPP sites. To ensure the completeness and consistency, validation frameworks, Code Scalability Applicability and Uncertainty (CSAU), and its regulatory guide, Evaluation Model Development and Assessment Process (EMDAP) are followed to guide validation activities and to make final code adequacy assessment. First, an external-flooding scenario is designed, and SPH simulations are performed with an SPH-based software named Neutrino. A Phenomenon Identification and Ranking Table (PIRT) is created, and the surface-wave impacts are identified as one of the high-rank phenomena. At the same time, a performance measurement standard is created for measuring the code adequacy in informing safety decisions consistently and transparently. Next, numerical benchmarks are designed for assessing the code adequacy of SPH methods and corresponding software implementations on Neutrino. Next, code accuracy is evaluated by comparing simulation results from Neutrino against experimental measurements in each benchmark. Meanwhile, a scaling analysis is performed to determine a group of dimensionless number for characterizing important physics and to assess the applicability of validation database collected in reduced-scale facility to the prototypic scenario. Finally, results from all activities are brought together to make an adequacy decision. It is found that, based on the current evidence, SPH methods and associated Neutrino software can predict the unbroken surface-wave peak pressure onto stationary rigid with reasonable accuracy if the suggested sizes of particles are used. However, it is suggested by independent reviews that the validity of major assumptions in target applications need to be evaluated with large-scale experiments, and the relevancy of other phenomena like turbulence and air pockets need to be identified with more benchmarks. As for the SPH’s adequacy in predicting the impact forces on dynamic rigid, the available evidence is not sufficient to support the decisions.
2019
Lin, L; Dinh, N; Prescott, S; Bao, H; Montanari, N; Sampath, R
Assessment of smoothed particle hydrodynamics methods for simulating the external-flooding scenario Conference
Proc. of International Topical Meeting on Nuclear Reactor Thermal Hydraulics Proc. of International Topical Meeting on Nuclear Reactor Thermal Hydraulics, Portland, Oregon, 2019.
@conference{lin2019assessment,
title = {Assessment of smoothed particle hydrodynamics methods for simulating the external-flooding scenario},
author = {L Lin and N Dinh and S Prescott and H Bao and N Montanari and R Sampath},
year = {2019},
date = {2019-12-01},
publisher = {Proc. of International Topical Meeting on Nuclear Reactor Thermal Hydraulics},
address = {Portland, Oregon},
organization = {Proc. of International Topical Meeting on Nuclear Reactor Thermal Hydraulics},
keywords = {Neutrino},
pubstate = {published},
tppubtype = {conference}
}
Ryan, E; C.,
In: Nuclear Technology, 2019.
@article{ryan2019pope,
title = {Pope (2020), Coupling of the smoothed particle hydrodynamic code Neutrino and the risk analysis virtual environment for particle spacing optimization},
author = {E Ryan and C.},
url = {https://www.tandfonline.com/doi/abs/10.1080/00295450.2019.1704576},
year = {2019},
date = {2019-01-01},
journal = {Nuclear Technology},
publisher = {Nuclear Technology},
keywords = {},
pubstate = {published},
tppubtype = {article}
}
Sezen, H; Hur, J; Smith, C; Aldemir, T; Denning, R
In: Nuclear Engineering and Design, vol. 355, 2019.
@article{sezen2019computational,
title = {A computational risk assessment approach to the integration of seismic and flooding hazards with internal hazards, Nuclear Engineering and Design},
author = {H Sezen and J Hur and C Smith and T Aldemir and R Denning},
url = {https://www.sciencedirect.com/science/article/pii/S0029549319303760},
year = {2019},
date = {2019-01-01},
journal = {Nuclear Engineering and Design},
volume = {355},
keywords = {},
pubstate = {published},
tppubtype = {article}
}
Ryan, E; Savage, B; Smith, C; Pope, C
In: Annals of Nuclear Energy, vol. 126, 2019.
@article{ryan2019comparison,
title = {Comparison of free surface flow measurements and smoothed particle hydrodynamic simulation for potential nuclear power plant flooding simulation, Annals of Nuclear Energy},
author = {E Ryan and B Savage and C Smith and C Pope},
url = {https://www.sciencedirect.com/science/article/pii/S030645491830611X},
year = {2019},
date = {2019-01-01},
journal = {Annals of Nuclear Energy},
volume = {126},
keywords = {},
pubstate = {published},
tppubtype = {article}
}
Andre, M; Bardet, P; Sampath, R; Montanari, N; Lin, L; Prescott, S; Ryan, E
Validation of risk-informed safety margin characterization for flooding of nuclear power plants Proceedings
Proc. of International Topical Meeting on Nuclear Reactor Thermal Hydraulics Proc, Portland, Oregon, 2019.
BibTeX | Tags:
@proceedings{andre2019validation,
title = {Validation of risk-informed safety margin characterization for flooding of nuclear power plants},
author = {M Andre and P Bardet and R Sampath and N Montanari and L Lin and S Prescott and E Ryan},
year = {2019},
date = {2019-01-01},
publisher = {Proc},
address = {Portland, Oregon},
organization = {Proc. of International Topical Meeting on Nuclear Reactor Thermal Hydraulics},
keywords = {},
pubstate = {published},
tppubtype = {proceedings}
}
Ryan, E; Prescott, S; Andre, M; Bardet, P; Montanari, N; Sampath, R
Validation and determination of significant simulation parameters using the smoothed particle hydrodynamic code Neutrino Conference
Proc. of Structural Mechanics in Reactor Technology Proc. of Structural Mechanics in Reactor Technology, Charlotte, North Carolina, 2019.
BibTeX | Tags:
@conference{ryan2019validation,
title = {Validation and determination of significant simulation parameters using the smoothed particle hydrodynamic code Neutrino},
author = {E Ryan and S Prescott and M Andre and P Bardet and N Montanari and R Sampath},
year = {2019},
date = {2019-01-01},
publisher = {Proc. of Structural Mechanics in Reactor Technology},
address = {Charlotte, North Carolina},
organization = {Proc. of Structural Mechanics in Reactor Technology},
keywords = {},
pubstate = {published},
tppubtype = {conference}
}
Gartner, N; Montanari, N; Richier, M; Hugel, V; Sampath, R
Towards real-time simulation of physically realistic pressure applied to submerged bodies using explicit and semi-implicit SPH algorithms Proceedings
Proc. of OCEANS, Marseille, France, 2019.
BibTeX | Tags:
@proceedings{gartner2019towards,
title = {Towards real-time simulation of physically realistic pressure applied to submerged bodies using explicit and semi-implicit SPH algorithms},
author = {N Gartner and N Montanari and M Richier and V Hugel and R Sampath},
year = {2019},
date = {2019-01-01},
publisher = {Proc. of OCEANS},
address = {Marseille, France},
keywords = {},
pubstate = {published},
tppubtype = {proceedings}
}
Prescott, S; Biersdorf, J; Sampath, R
Industry fire modeling enhancement tools and methods Technical Report
2019.
@techreport{prescott2019industry,
title = {Industry fire modeling enhancement tools and methods},
author = {S Prescott and J Biersdorf and R Sampath},
url = {https://www.osti.gov/biblio/1546734-industry-fire-modeling-enhancement-tools-methods},
year = {2019},
date = {2019-01-01},
publisher = {U. S Dept of Energy},
keywords = {},
pubstate = {published},
tppubtype = {techreport}
}
2018
Montanari, N; Sampath, R; Calhoun, D; Prescott, S; Smith, C
Coupling large-scale and detailed site flooding simulations Proceedings
Probablistic Safety Assessment and Management , Proc. of Probabilistic Safety Assessment and Management, Los Angeles, CA, 2018.
BibTeX | Tags:
@proceedings{montanari2018coupling,
title = {Coupling large-scale and detailed site flooding simulations},
author = {N Montanari and R Sampath and D Calhoun and S Prescott and C Smith},
year = {2018},
date = {2018-09-01},
publisher = {, Proc. of Probabilistic Safety Assessment and Management},
address = {Los Angeles, CA},
organization = {Probablistic Safety Assessment and Management},
keywords = {},
pubstate = {published},
tppubtype = {proceedings}
}
Montanari, N; Sampath, R; Akinci, N; Prescott, S; Smith, C; Weglian, J
SPH-based flooding simulations in probabilistic risk assessment Proceedings
SPHERIC Proc. of 13th SPHERIC International Workshop, Galway, Ireland, 2018.
BibTeX | Tags:
@proceedings{montanari2018sphbased,
title = {SPH-based flooding simulations in probabilistic risk assessment},
author = {N Montanari and R Sampath and N Akinci and S Prescott and C Smith and J Weglian},
year = {2018},
date = {2018-01-01},
publisher = {Proc. of 13th SPHERIC International Workshop},
address = {Galway, Ireland},
organization = {SPHERIC},
series = {13},
keywords = {},
pubstate = {published},
tppubtype = {proceedings}
}
Prescott, S; Sampath, R; Biersdorf, J
Risk-informed systems analysis (RISA) dynamic fire PRA roadmap Technical Report
2018.
@techreport{prescott2018riskinformed,
title = {Risk-informed systems analysis (RISA) dynamic fire PRA roadmap},
author = {S Prescott and R Sampath and J Biersdorf},
url = {https://www.osti.gov/biblio/1467474-risk-informed-systems-analysis-risa-dynamic-fire-pra-roadmap},
year = {2018},
date = {2018-01-01},
publisher = {U. S Dept of Energy},
keywords = {},
pubstate = {published},
tppubtype = {techreport}
}
Pope, C; Savage, B; Jash, S; Johnson, B; Muchmore, C; Nichols, L; Ryan, E; Suresh, S; Tahhan, A; Tuladhar, R; Wells, A; Smith, C
Nuclear power plant component flooding fragility research Technical Report
2018.
@techreport{pope2018nuclear,
title = {Nuclear power plant component flooding fragility research},
author = {C Pope and B Savage and S Jash and B Johnson and C Muchmore and L Nichols and E Ryan and S Suresh and A Tahhan and R Tuladhar and A Wells and C Smith},
url = {https://www.osti.gov/biblio/1467486},
year = {2018},
date = {2018-01-01},
publisher = {U},
keywords = {},
pubstate = {published},
tppubtype = {techreport}
}
Yoo, J; Choi, Y -J
2018.
@techreport{yoochoi2018,
title = {Choi (2018), Advanced validation risk-informed approach for the flooding tool based upon smooth particle hydrodynamics: validation and development status of NEUTRINO},
author = {J Yoo and Y -J Choi},
url = {https://www.osti.gov/biblio/1467476-advanced-validation-risk-informed-approach-flooding-tool-based-upon-smooth-particle-hydrodynamics-validation-development-status-neutrino},
year = {2018},
date = {2018-01-01},
publisher = {U. S Dept of Energy},
keywords = {},
pubstate = {published},
tppubtype = {techreport}
}
Parisi, C; Prescott, S; Ma, Z; Coleman, J; Szilard, R; Smith, C
Risk-informed external hazards analysis by EEVE toolkit Technical Report
Idaho National Laboratory 2018.
@techreport{parisi2018riskinformed,
title = {Risk-informed external hazards analysis by EEVE toolkit},
author = {C Parisi and S Prescott and Z Ma and J Coleman and R Szilard and C Smith},
url = {https://www.osti.gov/biblio/1478777},
year = {2018},
date = {2018-01-01},
volume = {6.},
institution = {Idaho National Laboratory},
keywords = {},
pubstate = {published},
tppubtype = {techreport}
}
Gartner, Nicolas; Richier, Mathieu; Hugel, Vincent
Hydrodynamics parameter identification of submerged bodies: numerical methods comparison and friction model analysis Proceedings Article
In: IEEE/RSJ International Conference on Intelligent Robots and Systems (IROS), Madrid, Spain, 2018.
@inproceedings{Gartner18,
title = {Hydrodynamics parameter identification of submerged bodies: numerical methods comparison and friction model analysis},
author = {Nicolas Gartner and Mathieu Richier and Vincent Hugel},
doi = {10.1109/IROS.2018.8593770},
year = {2018},
date = {2018-01-01},
booktitle = {IEEE/RSJ International Conference on Intelligent Robots and Systems (IROS)},
address = {Madrid, Spain},
keywords = {},
pubstate = {published},
tppubtype = {inproceedings}
}
2017
Hess, S; Prescott, S; Smith, C; Lin, L; Dinh, N; Sampath, R; Montanari, N
Integrated use of modeling and simulation in high winds PRA Conference
vol. 9., PSA spical Meeting on Probabilistic Assessment and Analysis, Pittsburgh, PA, 2017.
BibTeX | Tags:
@conference{hess2017integrated,
title = {Integrated use of modeling and simulation in high winds PRA},
author = {S Hess and S Prescott and C Smith and L Lin and N Dinh and R Sampath and N Montanari},
year = {2017},
date = {2017-08-01},
journal = {Proc. of International Topical Meeting on Probabilistic Assessment and Analysis, Pittsburgh, Pennsylvania},
volume = {9.},
publisher = {spical Meeting on Probabilistic Assessment and Analysis},
address = {Pittsburgh, PA},
organization = {PSA},
keywords = {},
pubstate = {published},
tppubtype = {conference}
}
Dinh, Montanari Sampath Akinci Prescott N R N S 9. L. Lin N.
Assessment of smoothed particle hydrodynamics in application of high-wind risk analysis Conference
NURETH Proc. of International Topical Meeting on Nuclear Reactor Thermal Hydraulics, Pittsburgh, PA, 2017.
BibTeX | Tags:
@conference{llin2016psa,
title = {Assessment of smoothed particle hydrodynamics in application of high-wind risk analysis},
author = {Montanari Sampath Akinci Prescott N R N S 9.L. Lin N. Dinh},
year = {2017},
date = {2017-08-01},
publisher = {Proc. of International Topical Meeting on Nuclear Reactor Thermal Hydraulics},
address = {Pittsburgh, PA},
organization = {NURETH},
keywords = {},
pubstate = {published},
tppubtype = {conference}
}
Montanari, N; Sampath, R; Weglian, J; Wolfgang, R; Dube, D; Smith, C; Prescott, S
Coupling smoothed-particle hydrodynamics and Torricelli�s law-based hydraulic models for flooding risk analysis Proceedings
PSA Proc. of International Topical Meeting on Probabilistic Assessment and Analysis, Pittsburgh, Pennsylvania, 2017.
BibTeX | Tags:
@proceedings{montanari2017coupling,
title = {Coupling smoothed-particle hydrodynamics and Torricelli�s law-based hydraulic models for flooding risk analysis},
author = {N Montanari and R Sampath and J Weglian and R Wolfgang and D Dube and C Smith and S Prescott},
year = {2017},
date = {2017-01-01},
publisher = {Proc. of International Topical Meeting on Probabilistic Assessment and Analysis},
address = {Pittsburgh, Pennsylvania},
organization = {PSA},
keywords = {},
pubstate = {published},
tppubtype = {proceedings}
}
Parisi, C; Prescott, S; Ma, Z; Spears, B; Szilard, R; Coleman, J; Kosbab, B
Risk-informed external hazards analysis for seismic and flooding phenomena for a generic PWR Technical Report
2017.
@techreport{parisi2017riskinformed,
title = {Risk-informed external hazards analysis for seismic and flooding phenomena for a generic PWR},
author = {C Parisi and S Prescott and Z Ma and B Spears and R Szilard and J Coleman and B Kosbab},
url = {https://www.osti.gov/biblio/1376899},
year = {2017},
date = {2017-01-01},
publisher = {U. S Dept of Energy},
keywords = {},
pubstate = {published},
tppubtype = {techreport}
}
Sampath, Montanari N 6. J. Weglian R.
Investigation into the use of three-dimensional modeling techniques to assess internal flooding scenarios Technical Report
Electric Power Research Institute 2017.
@techreport{weglian2017,
title = {Investigation into the use of three-dimensional modeling techniques to assess internal flooding scenarios},
author = {Montanari N 6.J. Weglian R. Sampath},
url = {https://www.epri.com/#/pages/product/000000003002010673/},
year = {2017},
date = {2017-01-01},
institution = {Electric Power Research Institute},
keywords = {},
pubstate = {published},
tppubtype = {techreport}
}
2016
Sampath, R; Montanari, N; Akinci, N; Prescott, S; Smith, C
Large-scale solitary wave simulation with implicit incompressible SPH, Journal of Ocean Engineering and Marine Energy Journal Article
In: Journal of Ocean Engineering and Marine Energy, vol. 2, no. 3, 2016.
@article{sampath2016largescale,
title = {Large-scale solitary wave simulation with implicit incompressible SPH, Journal of Ocean Engineering and Marine Energy},
author = {R Sampath and N Montanari and N Akinci and S Prescott and C Smith},
url = {https://link.springer.com/article/10.1007/s40722-016-0060-8},
year = {2016},
date = {2016-01-01},
journal = {Journal of Ocean Engineering and Marine Energy},
volume = {2},
number = {3},
keywords = {},
pubstate = {published},
tppubtype = {article}
}
Lin, L; Dinh, N; Sampath, R; Akinci, N
A computational study of thin film dynamics on micro-structured surfaces Proceedings
ASME Proc. of ASME Heat Transfer, Washington DC, USA, 2016.
BibTeX | Tags:
@proceedings{lin2016computational,
title = {A computational study of thin film dynamics on micro-structured surfaces},
author = {L Lin and N Dinh and R Sampath and N Akinci},
year = {2016},
date = {2016-01-01},
publisher = {Proc. of ASME Heat Transfer},
address = {Washington DC, USA},
organization = {ASME},
keywords = {},
pubstate = {published},
tppubtype = {proceedings}
}
Hess, S; Lin, L; Sampath, R; Prescott, S; Smith, C
Smoothed-particle hydrodynamics based wind representation Technical Report
2016.
@techreport{hess2016smoothedparticle,
title = {Smoothed-particle hydrodynamics based wind representation},
author = {S Hess and L Lin and R Sampath and S Prescott and C Smith},
url = {https://lwrs.inl.gov/RiskInformed Safety Margin Characterization/Smoothed-particle_Hydrodynamics_based_Wind_Representation.pdf},
year = {2016},
date = {2016-01-01},
publisher = {U.S. Department of Energy},
keywords = {},
pubstate = {published},
tppubtype = {techreport}
}
Coleman, J; Bolisetti, C; Veeraraghavan, S; Parisi, C; Prescott, S; Gupta, A
Multi-hazard advanced seismic probabilistic risk assessment tools and applications Technical Report
Idaho National Laboratory 2016.
@techreport{coleman2016multihazard,
title = {Multi-hazard advanced seismic probabilistic risk assessment tools and applications},
author = {J Coleman and C Bolisetti and S Veeraraghavan and C Parisi and S Prescott and A Gupta},
url = {https://www.osti.gov/biblio/1369534},
year = {2016},
date = {2016-01-01},
publisher = {U. S Department of Energy},
institution = {Idaho National Laboratory},
keywords = {},
pubstate = {published},
tppubtype = {techreport}
}
2015
Prescott, S; Smith, C; Sampath, R
Incorporating dynamic 3Đ simulation into PRA Conference
PSAM Proc. of International Topical Meeting on Probabilistic Assessment and Analysis, Sun Valley, ID, USA, 2015.
BibTeX | Tags:
@conference{prescott2015incorporating,
title = {Incorporating dynamic 3Đ simulation into PRA},
author = {S Prescott and C Smith and R Sampath},
year = {2015},
date = {2015-01-01},
publisher = {Proc. of International Topical Meeting on Probabilistic Assessment and Analysis},
address = {Sun Valley, ID, USA},
organization = {PSAM},
keywords = {},
pubstate = {published},
tppubtype = {conference}
}
Smith, C; Prescott, S; Ryan, E; Calhoun, D; Sampath, R; Danielle, A; Casteneda, C
Flooding capability for river-based scenarios Technical Report
2015.
@techreport{smith2015flooding,
title = {Flooding capability for river-based scenarios},
author = {C Smith and S Prescott and E Ryan and D Calhoun and R Sampath and A Danielle and C Casteneda},
url = {https://www.osti.gov/biblio/1245528},
year = {2015},
date = {2015-01-01},
publisher = {U. S Department of Energy},
keywords = {},
pubstate = {published},
tppubtype = {techreport}
}
Coleman, J; Prescott, S; Smith, C; Sampath, R
Demonstration of coupled multievent scenario at a subject nuclear power plant Technical Report
Idaho National Laboratory 2015.
@techreport{coleman2015demonstration,
title = {Demonstration of coupled multievent scenario at a subject nuclear power plant},
author = {J Coleman and S Prescott and C Smith and R Sampath},
url = {https://www.osti.gov/biblio/1371514},
year = {2015},
date = {2015-01-01},
publisher = {U. S Department of Energy},
institution = {Idaho National Laboratory},
keywords = {},
pubstate = {published},
tppubtype = {techreport}
}
Smith, C; Prescott, S; Kvarfordt, K; Sampath, R; Larson, K
Status of the phenomena representation, 3Đ modeling, and cloud-based software architecture development Technical Report
Idaho National Laboratory 2015.
@techreport{smith2015status,
title = {Status of the phenomena representation, 3Đ modeling, and cloud-based software architecture development},
author = {C Smith and S Prescott and K Kvarfordt and R Sampath and K Larson},
url = {https://www.osti.gov/biblio/1245516},
year = {2015},
date = {2015-01-01},
publisher = {U. S Department of Energy},
institution = {Idaho National Laboratory},
keywords = {},
pubstate = {published},
tppubtype = {techreport}
}
Smith, C; Prescott, S; Coleman, J; Ryan, E; Bhandari, B; Sludern, D; Pope, C; Sampath, R
Progress for the industry application external hazard analyses early demonstration Technical Report
Idaho National Laboratory 2015.
@techreport{smith2015progress,
title = {Progress for the industry application external hazard analyses early demonstration},
author = {C Smith and S Prescott and J Coleman and E Ryan and B Bhandari and D Sludern and C Pope and R Sampath},
url = {https://www.osti.gov/biblio/1245520},
year = {2015},
date = {2015-01-01},
publisher = {U. S Department of Energy},
institution = {Idaho National Laboratory},
keywords = {},
pubstate = {published},
tppubtype = {techreport}
}
Prescott, S; Mandelli, D; Sampath, R; Smith, C; Lin, L
3D simulation of external flooding events for the RISMC pathway Technical Report
Idaho National Laboratory 2015.
@techreport{prescott20153d,
title = {3D simulation of external flooding events for the RISMC pathway},
author = {S Prescott and D Mandelli and R Sampath and C Smith and L Lin},
url = {https://www.osti.gov/biblio/1244638},
year = {2015},
date = {2015-01-01},
publisher = {U. S Department of Energy},
institution = {Idaho National Laboratory},
keywords = {},
pubstate = {published},
tppubtype = {techreport}
}
2014
Prescott, S; Sampath, R; Smith, C; Koonce, T
Prototype development capabilities of 3Đ spatial interactions and failures during scenario simulation Technical Report
Idaho National Laboratory 2014.
@techreport{prescott2014prototype,
title = {Prototype development capabilities of 3Đ spatial interactions and failures during scenario simulation},
author = {S Prescott and R Sampath and C Smith and T Koonce},
url = {https://www.osti.gov/biblio/1166044},
year = {2014},
date = {2014-01-01},
publisher = {U.S Department of Energy},
institution = {Idaho National Laboratory},
keywords = {},
pubstate = {published},
tppubtype = {techreport}
}
Prescott, S; Sampath, R; Smith, C; Yang, T
3D modeling engine representation summary report Technical Report
Idaho National Laboratory 2014.
@techreport{prescott20143d,
title = {3D modeling engine representation summary report},
author = {S Prescott and R Sampath and C Smith and T Yang},
url = {https://www.osti.gov/biblio/1166048},
year = {2014},
date = {2014-01-01},
publisher = {U. S Department of Energy},
institution = {Idaho National Laboratory},
keywords = {},
pubstate = {published},
tppubtype = {techreport}
}