Development of an Advanced Computational Fluid Dynamics Technology for the Next-Generation Nuclear Reactor System Analysis and Safety Margin Characterization Code

Development of an Advanced Computational Fluid Dynamics Technology for the Next-Generation Nuclear Reactor System Analysis and Safety Margin Characterization Code
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Total Pages: 14
Release: 2015
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This report describes the research activities we have conducted at NCSU for our NEUP project. The work toward achieving the objectives of the project is reported. The significant achievements and accomplishments are presented. A number of numerical experiments are conducted to demonstrate that the goal of the proposed work has been successfully achieved. Issues, recommendations, and future work are discussed.


Development of an Advanced Computational Fluid Dynamics Technology for the Next-Generation Nuclear Reactor System Analysis and Safety Margin Characterization Code
Language: en
Pages: 14
Authors:
Categories:
Type: BOOK - Published: 2015 - Publisher:

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This report describes the research activities we have conducted at NCSU for our NEUP project. The work toward achieving the objectives of the project is reporte
Advances of Computational Fluid Dynamics in Nuclear Reactor Design and Safety Assessment
Language: en
Pages: 888
Authors: Jyeshtharaj Joshi
Categories: Science
Type: BOOK - Published: 2019-06-15 - Publisher: Woodhead Publishing

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Advances of Computational Fluid Dynamics in Nuclear Reactor Design and Safety Assessment presents the latest computational fluid dynamic technologies. It includ
Summary Review on the Application of Computational Fluid Dynamics in Nuclear Power Plant Design
Language: en
Pages: 121
Authors: IAEA
Categories: Business & Economics
Type: BOOK - Published: 2022-03-28 - Publisher: International Atomic Energy Agency

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This publication documents the results of an IAEA coordinated research project (CRP)on the application of computational fluid dynamics (CFD) codes for nuclear p
Use of Computational Fluid Dynamics Codes for Safety Analysis of Nuclear Reactor Systems
Language: en
Pages: 66
Authors:
Categories: Abstracts
Type: BOOK - Published: 2003 - Publisher:

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Presets the report of the joint IAEA and OECD/NEA technical meeting on the Use of CFD Codes for Safety Analysis of Reactor Systems, including Containment, held
Processes and Procedures for Application of CFD to Nuclear Reactor Safety Analysis
Language: en
Pages:
Authors: Richard W. Johnson
Categories:
Type: BOOK - Published: 2006 - Publisher:

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Traditionally, nuclear reactor safety analysis has been performed using systems analysis codes such as RELAP5, which was developed at the INL. However, goals es