Comparative Study of Neutronics Analysis Techniques for Radioactive Waste Assessment
Autor: | B. Colling, Mark R. Gilbert, S. Zheng, J. Naish, T. Eade |
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Rok vydání: | 2018 |
Předmět: |
Nuclear and High Energy Physics
Neutron transport Solid geometry Computer science business.industry Mechanical Engineering Radioactive waste 01 natural sciences 010305 fluids & plasmas Nuclear Energy and Engineering Component (UML) 0103 physical sciences Unstructured mesh General Materials Science 010306 general physics Process engineering business ComputingMethodologies_COMPUTERGRAPHICS Civil and Structural Engineering |
Zdroj: | Fusion Science and Technology. 74:330-339 |
ISSN: | 1943-7641 1536-1055 |
Popis: | Computational models created for neutronics assessment through solid geometry conversion are often specific to the analysis being performed. The use of unstructured mesh geometry has the potential to reduce the build time of MCNP models, reduce inaccuracies introduced through flux averaging over different components and material mixing, and make use of computer-aided design models that can also be suitable for other types of analysis. In this paper three neutronics methods were investigated for suitability in performing a radioactive waste assessment of a fusion demonstration reactor. The methods included the conventional cell-based approach, a superimposed structured mesh, and the use of a recently developed capability with unstructured mesh geometry. It was concluded that an unstructured mesh approach has the potential to be an important tool for assessing radioactive waste to inform reactor and component design. |
Databáze: | OpenAIRE |
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