Three-dimensional all-speed CFD code for safety analysis of nuclear reactor containment: Status of GASFLOW parallelization, model development, validation and application

Abstract There has been a growing interest in assessing the risks to the marine environment from produced water discharges. This study describes the development of a numerical approach, POM-RW, based on an integration of the Princeton Ocean Model (POM) and a Random Walk (RW) simulation of pollutant transport. Specifically, the POM is employed to simulate local ocean currents. It provides three-dimensional hydrodynamic input to a Random Walk model focused on the dispersion of toxic components within the produced water stream on a regional spatial scale. Model development and field validation of the predicted current field and pollutant concentrations were conducted in conjunction with a water quality and ecological monitoring program for an offshore facility located on the Grand Banks of Canada. Results indicate that the POM-RW approach is useful to address environmental risks associated with the produced water discharges.

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The ICON Single-Column Mode

Atmosphere ◽

10.3390/atmos12070906 ◽

2021 ◽

Vol 12 (7) ◽

pp. 906

Author(s):

Ivan Bašták Ďurán ◽

Martin Köhler ◽

Astrid Eichhorn-Müller ◽

Vera Maurer ◽

Juerg Schmidli ◽

...

Keyword(s):

Data Storage ◽

Model Development ◽

Computational Cost ◽

Three Dimensional ◽

Shallow Convection ◽

Modeling Framework ◽

Additional Tool ◽

Eddy Simulation ◽

Single Column ◽

Stratocumulus Clouds

The single-column mode (SCM) of the ICON (ICOsahedral Nonhydrostatic) modeling framework is presented. The primary purpose of the ICON SCM is to use it as a tool for research, model evaluation and development. Thanks to the simplified geometry of the ICON SCM, various aspects of the ICON model, in particular the model physics, can be studied in a well-controlled environment. Additionally, the ICON SCM has a reduced computational cost and a low data storage demand. The ICON SCM can be utilized for idealized cases—several well-established cases are already included—or for semi-realistic cases based on analyses or model forecasts. As the case setup is defined by a single NetCDF file, new cases can be prepared easily by the modification of this file. We demonstrate the usage of the ICON SCM for different idealized cases such as shallow convection, stratocumulus clouds, and radiative transfer. Additionally, the ICON SCM is tested for a semi-realistic case together with an equivalent three-dimensional setup and the large eddy simulation mode of ICON. Such consistent comparisons across the hierarchy of ICON configurations are very helpful for model development. The ICON SCM will be implemented into the operational ICON model and will serve as an additional tool for advancing the development of the ICON model.

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Development and Application of Multi-Physics Safety Analysis Code for Advanced Liquid Metal Cooled Reactor

Volume 6B: Thermal-Hydraulics and Safety Analyses ◽

10.1115/icone26-81973 ◽

2018 ◽

Author(s):

Chi Wang ◽

Xuebei Zhang ◽

Jingchao Feng ◽

Muhammad Shehzad Khan ◽

Minyou Ye ◽

...

Keyword(s):

Nuclear Reactor ◽

Safety Analysis ◽

Coolant Temperature ◽

Medium Size ◽

High Tech ◽

Fuel Temperature ◽

Flow Phenomena ◽

Nuclear Reactor Safety ◽

Cfd Method ◽

Point Kinetics

The simulation of 3D thermal-hydraulic problem for the pool type fast reactors, is one of the necessary and great importance. Most system codes can’t be used to simulate multi-dimensional thermal-hydraulics problems, whereas, the CFD method is suitable to deal with these type of simulation challenges. Based on the CFD method, a neutronics and thermohydraulic coupling code FLUENT/PK for nuclear reactor safety analysis by coupling the commercial CFD code FLUENT with the point kinetics model (PKM) and the pin thermal model (PTM) is developed by University of Science and Technology of China (USTC). The coupled code is verified by comparing with a series of benchmarks on beam interruptions in a lead-bismuth-cooled and MOX-fuelled accelerator-driven system. The variations of transient power, fuel temperature and outlet coolant temperature all agree well with the benchmark results. The validation results show that the code can be used to simulate the transient accidents of critical and sub-critical lead/lead-bismuth cooled reactors. Then this coupling code is used to evaluate the safety performance of MYRRHA (Multi-purpose Hybrid Research Reactor for High-tech Applications) at unprotected beam over-power (UBOP) accident, and M2LFR-1000 (Medium-size Modular Lead-cooled Fast Reactor) at the unprotected transient over-power (UTOP) and unprotected loss of flow (ULOF) accident. The transient power, the temperature of coolant and fuel and multi-dimensional flow phenomena in upper plenum and lower plenum are presented and discussed in this paper.

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Non-fickian three-dimensional hindered moisture absorption in polymeric composites: Model development and validation

Polymer Composites ◽

10.1002/pc.22523 ◽

2013 ◽

Vol 34 (7) ◽

pp. 1144-1157 ◽

Cited By ~ 16

Author(s):

L.R. Grace ◽

M.C. Altan

Keyword(s):

Moisture Absorption ◽

Model Development ◽

Three Dimensional ◽

Polymeric Composites ◽

Development And Validation

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Electrochemical nucleation and three-dimensional growth of metal nanoparticles under mixed kinetic-diffusion control: model development and validation

Electrochimica Acta ◽

10.1016/j.electacta.2016.04.094 ◽

2016 ◽

Vol 206 ◽

pp. 116-126 ◽

Cited By ~ 32

Author(s):

Pietro Altimari ◽

Francesca Pagnanelli

Keyword(s):

Metal Nanoparticles ◽

Model Development ◽

Three Dimensional ◽

Control Model ◽

Diffusion Control ◽

Electrochemical Nucleation ◽

Dimensional Growth ◽

Kinetic Diffusion ◽

Development And Validation

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Neutronic safety analysis of proposed reactor technologies for Ghana’s nuclear power plant using the MCNP code

Nuclear Technology and Radiation Protection ◽

10.2298/ntrp190108029a ◽

2019 ◽

Vol 34 (3) ◽

pp. 238-242

Author(s):

Rex Abrefah ◽

Prince Atsu ◽

Robert Sogbadji

Keyword(s):

High Pressure ◽

Power Plant ◽

Nuclear Power Plant ◽

Nuclear Power ◽

Nuclear Reactor ◽

Atomic Energy Commission ◽

Clean Energy ◽

Safety Analysis ◽

Operating Conditions ◽

The Government

In pursuance of sufficient, stable and clean energy to solve the ever-looming power crisis in Ghana, the Nuclear Power Institute of the Ghana Atomic Energy Commission has on the agenda to advise the government on the nuclear power to include in the country's energy mix. After consideration of several proposed nuclear reactor technologies, the Nuclear Power Institute considered a high pressure reactor or vodo-vodyanoi energetichesky reactor as the nuclear power technologies for Ghana's first nuclear power plant. As part of technology assessments, neutronic safety parameters of both reactors are investigated. The MCNP neutronic code was employed as a computational tool to analyze the reactivity temperature coefficients, moderator void coefficient, criticality and neutron behavior at various operating conditions. The high pressure reactor which is still under construction and theoretical safety analysis, showed good inherent safety features which are comparable to the already existing European pressurized reactor technology.

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A Conceptual Framework for Integration Development of GSFLOW Model: Concerns and Issues Identified and Addressed for Model Development Efficiency

10.5194/gmd-2018-268 ◽

2018 ◽

Author(s):

Chao Chen ◽

Sajjad Ahmad ◽

Ajay Kalra

Keyword(s):

Groundwater Flow ◽

Conceptual Framework ◽

Critical Role ◽

Model Development ◽

Three Dimensional ◽

Data Communication ◽

Flow Simulation ◽

Creek Watershed ◽

Surface Water Flow ◽

Computation Algorithms

Abstract. In Coupled Groundwater and Surface-Water Flow (GSFLOW) model, the three-dimensional finite-difference groundwater model (MODFLOW) plays a critical role of groundwater flow simulation, together with which the Precipitation-Runoff Modeling System (PRMS) simulates the surface hydrologic processes. While the model development of each individual PRMS and MODFLOW model requires tremendous time and efforts, further integration development of these two models exerts additional concerns and issues due to different simulation realm, data communication, and computation algorithms. To address these concerns and issues in GSFLOW, the present paper proposes a conceptual framework from perspectives of: Model Conceptualization, Data Linkages and Transference, Model Calibration, and Sensitivity Analysis. As a demonstration, a MODFLOW groundwater flow system was developed and coupled with the PRMS model in the Lehman Creek watershed, eastern Nevada, resulting in a smooth and efficient integration as the hydrogeologic features were well captured and represented. The proposed conceptual integration framework with techniques and concerns identified substantially improves GSFLOW model development efficiency and help better model result interpretations. This may also find applications in other integrated hydrologic modelings.

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