scholarly journals Verification and Validation of High-Fidelity Multi-Physics Simulation Codes for Advanced Nuclear Reactors (Year 2)

2014 ◽  
Author(s):  
C. H. Lee ◽  
H. C. Lee
Keyword(s):  
Nuclear Reactors ◽  
Verification And Validation ◽  
High Fidelity ◽  
Physics Simulation ◽  
Simulation Codes

scholarly journals Innovations in Multi-Physics Methods Development, Validation, and Uncertainty Quantification

2021 ◽  
Vol 2 (1) ◽  
pp. 44-56
Author(s):  
Maria Avramova ◽  
Agustin Abarca ◽  
Jason Hou ◽  
Kostadin Ivanov
Keyword(s):  
Uncertainty Quantification ◽  
Spatial Scale ◽  
Data Science ◽  
Nuclear Reactor ◽  
High Fidelity ◽  
Energy Agency ◽  
Multi Scale ◽  
Physics Simulation ◽  
Safety Parameters ◽  
Impact Problems

This paper provides a review of current and upcoming innovations in development, validation, and uncertainty quantification of nuclear reactor multi-physics simulation methods. Multi-physics modelling and simulations (M&S) provide more accurate and realistic predictions of the nuclear reactors behavior including local safety parameters. Multi-physics M&S tools can be subdivided in two groups: traditional multi-physics M&S on assembly/channel spatial scale (currently used in industry and regulation), and novel high-fidelity multi-physics M&S on pin (sub-pin)/sub-channel spatial scale. The current trends in reactor design and safety analysis are towards further development, verification, and validation of multi-physics multi-scale M&S combined with uncertainty quantification and propagation. Approaches currently applied for validation of the traditional multi-physics M&S are summarized and illustrated using established Nuclear Energy Agency/Organization for Economic Cooperation and Development (NEA/OECD) multi-physics benchmarks. Novel high-fidelity multi-physics M&S allow for insights crucial to resolve industry challenge and high impact problems previously impossible with the traditional tools. Challenges in validation of novel multi-physics M&S are discussed along with the needs for developing validation benchmarks based on experimental data. Due to their complexity, the novel multi-physics codes are still computationally expensive for routine applications. This fact motivates the use of high-fidelity novel models and codes to inform the low-fidelity traditional models and codes, leading to improved traditional multi-physics M&S. The uncertainty quantification and propagation across different scales (multi-scale) and multi-physics phenomena are demonstrated using the OECD/NEA Light Water Reactor Uncertainty Analysis in Modelling benchmark framework. Finally, the increasing role of data science and analytics techniques in development and validation of multi-physics M&S is summarized.

scholarly journals Enhanced verification test suite for physics simulation codes

2008 ◽  
Author(s):  
James R. Kamm ◽  
Jerry S. Brock ◽  
Scott T. Brandon ◽  
David L. Cotrell ◽  
Bryan Johnson ◽  
...  
Keyword(s):  
Test Suite ◽  
Physics Simulation ◽  
Verification Test ◽  
Simulation Codes

scholarly journals Wind Energy High-Fidelity Model Verification and Validation Roadmap

2020 ◽  
Author(s):  
David Charles Maniaci ◽  
Patrick J. Moriarty ◽  
Matthew F. Barone ◽  
Matthew J. Churchfield ◽  
Michael A. Sprague ◽  
...  
Keyword(s):  
Wind Energy ◽  
Model Verification ◽  
Verification And Validation ◽  
High Fidelity ◽  
Model Verification And Validation ◽  
Fidelity Model

scholarly journals A HIGH-FIDELITY SIMULATION OF THE C5G7 BENCHMARK BY USING THE PARALLEL ENTER CODE

2021 ◽  
Vol 247 ◽  
pp. 06023
Author(s):  
Zhenglin Ruan ◽  
Haibing Guo
Keyword(s):  
Large Scale ◽  
High Efficiency ◽  
Nuclear Reactors ◽  
Neutron Transport ◽  
Reaction Cross ◽  
High Fidelity ◽  
Control Rod ◽  
Section Data ◽  
Transport Code ◽  
Deterministic Transport

In simulation of advanced nuclear reactors, requirements like high precision, high efficiency and convenient to multi-physics coupling are putting forward. The deterministic transport method has the advantage of high efficiency, capable of obtaining detailed flux distribution and efficient in multi-physics coupling, but its accuracy is limited by the homogenized reaction cross-section data and core modelling exactness. The traditional two-steps homogenization strategy may introduce substantial deviation during the assembly calculation. It is possible to conduct a whole core deterministic transport simulation pin-by-pin to achieve higher accuracy, which eliminates the assembly homogenization process. The C5G7 benchmarks were proposed to test the ability of a modern deterministic transport code in analyzing whole core reactor problems without spatial homogenization. Different deterministic code that developed by different methods were applied to the benchmark simulation and some of them solved the benchmark accurately. However, there still exist some drawbacks in the given calculation processes which carried out by some other deterministic transport codes and we could find that the fuel pin cell in the assembly were not exactly geometrically modelled owing to the limit of the code. Consequently, the calculation precision could be improved by utilizing a high-fidelity geometry modelling. In this paper, the C5G7 benchmarks with different control rod position and different configuration were calculated by the finite element SN neutron transport code ENTER [1], and the results were presented after massively parallel computation on TIANHE-II supercomputer. By introducing a large scale high-fidelity unstructured meshes, high fidelity distributions of power and neutron flux were gained and compared with the results from other codes, excellent consistency were observed. To sum up, the ENTER code can meet those new requirements in simulation of advanced nuclear reactors and more works and researches will be implemented for a further improvement.

scholarly journals High Fidelity Physics Simulation of 128 Channel MIMO Sensor for 77GHz Automotive Radar

IEEE Access ◽  
2020 ◽  
Vol 8 ◽  
pp. 160643-160652
Author(s):  
Ushemadzoro Chipengo ◽  
Arien Sligar ◽  
Shawn Carpenter
Keyword(s):  
High Fidelity ◽  
Automotive Radar ◽  
Physics Simulation

scholarly journals EVALUATION OF THE ESFR END OF CYCLE STATE AND DETAILED ANALYSIS OF SPATIAL DISTRIBUTIONS OF REACTIVITY COEFFICIENTS

2021 ◽  
Vol 247 ◽  
pp. 02001
Author(s):  
Una Davies ◽  
Marat Margulis ◽  
Eugene Shwageraus ◽  
Emil Fridman ◽  
Nuria Garcia-Herranz ◽  
...  
Keyword(s):  
Detailed Analysis ◽  
Spatial Distributions ◽  
Reactor Physics ◽  
Physics Simulation ◽  
Reactivity Coefficients ◽  
High Degree ◽  
Commercial Size ◽  
Simulation Codes

The ESFR-SMART project is the latest iteration of research into the behaviour of a commercial-size SFR core throughout its lifetime. As part of this project the ESFR core has been modelled by a range of different reactor physics simulation codes at its end of cycle state, and the important safety relevant parameters evaluated. These parameters are found to agree well between the different codes, giving good confidence in the results. A detailed mapping of the local sodium void worth is also performed due to the problems associated with the positive void coefficient seen in large SFR designs. The local void worth maps show that the use of zone-wise coefficients replicates the important reactivity feedbacks to a high degree, indicating their suitability for use in SFR simulations.

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