Benchmark description of a stylized three-dimensional European Pressurized Reactor (EPR) problem
This paper describes a whole-core, three-dimensional, code-to-code benchmark problem based on the European Pressurized Reactor (EPR) developed by AREVA NP. The core specifications were taken directly from the Final Safety Analysis Report (FSAR) submitted to the Nuclear Regulatory Commission (NRC) an...
Ausführliche Beschreibung
Gespeichert in:
| Autor*in: |
Lago, Daniel [verfasserIn] |
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| Format: |
E-Artikel |
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| Sprache: |
Englisch |
| Erschienen: |
2016transfer abstract |
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| Schlagwörter: |
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| Umfang: |
29 |
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| Übergeordnetes Werk: |
Enthalten in: Histone deacetylase 5 is a phosphorylation substrate of protein kinase D in osteoclasts - Meyers, Carina Mello Guimaraes ELSEVIER, 2022, the international review journal covering all aspects of nuclear energy, Amsterdam [u.a.] |
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| Übergeordnetes Werk: |
volume:93 ; year:2016 ; pages:18-46 ; extent:29 |
| Links: |
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| DOI / URN: |
10.1016/j.pnucene.2016.07.009 |
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ELV035087269 |
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| 520 | |a This paper describes a whole-core, three-dimensional, code-to-code benchmark problem based on the European Pressurized Reactor (EPR) developed by AREVA NP. The core specifications were taken directly from the Final Safety Analysis Report (FSAR) submitted to the Nuclear Regulatory Commission (NRC) and the reactor core was modeled in a stylized manner while maintaining full heterogeneity at the pin and assembly level. Three different fresh core control rod configurations are presented in this paper – All Rods Out (ARO), Some Rods In (SRI), and All Rods In (ARI). Detailed Monte Carlo results are presented and include core eigenvalues, pin fission densities, and assembly averaged fission distributions. The benchmark results together with the provided macroscopic cross section libraries are useful for testing the numerical accuracy of transport solution methods for criticality analysis. The benchmark description includes the material atom densities and other relevant parameters for cross section studies. | ||
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10.1016/j.pnucene.2016.07.009 doi GBVA2016004000014.pica (DE-627)ELV035087269 (ELSEVIER)S0149-1970(16)30152-4 DE-627 ger DE-627 rakwb eng 620 620 DE-600 610 VZ 44.83 bkl Lago, Daniel verfasserin aut Benchmark description of a stylized three-dimensional European Pressurized Reactor (EPR) problem 2016transfer abstract 29 nicht spezifiziert zzz rdacontent nicht spezifiziert z rdamedia nicht spezifiziert zu rdacarrier This paper describes a whole-core, three-dimensional, code-to-code benchmark problem based on the European Pressurized Reactor (EPR) developed by AREVA NP. The core specifications were taken directly from the Final Safety Analysis Report (FSAR) submitted to the Nuclear Regulatory Commission (NRC) and the reactor core was modeled in a stylized manner while maintaining full heterogeneity at the pin and assembly level. Three different fresh core control rod configurations are presented in this paper – All Rods Out (ARO), Some Rods In (SRI), and All Rods In (ARI). Detailed Monte Carlo results are presented and include core eigenvalues, pin fission densities, and assembly averaged fission distributions. The benchmark results together with the provided macroscopic cross section libraries are useful for testing the numerical accuracy of transport solution methods for criticality analysis. The benchmark description includes the material atom densities and other relevant parameters for cross section studies. This paper describes a whole-core, three-dimensional, code-to-code benchmark problem based on the European Pressurized Reactor (EPR) developed by AREVA NP. The core specifications were taken directly from the Final Safety Analysis Report (FSAR) submitted to the Nuclear Regulatory Commission (NRC) and the reactor core was modeled in a stylized manner while maintaining full heterogeneity at the pin and assembly level. Three different fresh core control rod configurations are presented in this paper – All Rods Out (ARO), Some Rods In (SRI), and All Rods In (ARI). Detailed Monte Carlo results are presented and include core eigenvalues, pin fission densities, and assembly averaged fission distributions. The benchmark results together with the provided macroscopic cross section libraries are useful for testing the numerical accuracy of transport solution methods for criticality analysis. The benchmark description includes the material atom densities and other relevant parameters for cross section studies. EPR Elsevier Benchmark Elsevier PWR Elsevier Rahnema, Farzad oth Enthalten in Elsevier Science Meyers, Carina Mello Guimaraes ELSEVIER Histone deacetylase 5 is a phosphorylation substrate of protein kinase D in osteoclasts 2022 the international review journal covering all aspects of nuclear energy Amsterdam [u.a.] (DE-627)ELV007755775 volume:93 year:2016 pages:18-46 extent:29 https://doi.org/10.1016/j.pnucene.2016.07.009 Volltext GBV_USEFLAG_U GBV_ELV SYSFLAG_U SSG-OLC-PHA 44.83 Rheumatologie Orthopädie VZ AR 93 2016 18-46 29 045F 620 |
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10.1016/j.pnucene.2016.07.009 doi GBVA2016004000014.pica (DE-627)ELV035087269 (ELSEVIER)S0149-1970(16)30152-4 DE-627 ger DE-627 rakwb eng 620 620 DE-600 610 VZ 44.83 bkl Lago, Daniel verfasserin aut Benchmark description of a stylized three-dimensional European Pressurized Reactor (EPR) problem 2016transfer abstract 29 nicht spezifiziert zzz rdacontent nicht spezifiziert z rdamedia nicht spezifiziert zu rdacarrier This paper describes a whole-core, three-dimensional, code-to-code benchmark problem based on the European Pressurized Reactor (EPR) developed by AREVA NP. The core specifications were taken directly from the Final Safety Analysis Report (FSAR) submitted to the Nuclear Regulatory Commission (NRC) and the reactor core was modeled in a stylized manner while maintaining full heterogeneity at the pin and assembly level. Three different fresh core control rod configurations are presented in this paper – All Rods Out (ARO), Some Rods In (SRI), and All Rods In (ARI). Detailed Monte Carlo results are presented and include core eigenvalues, pin fission densities, and assembly averaged fission distributions. The benchmark results together with the provided macroscopic cross section libraries are useful for testing the numerical accuracy of transport solution methods for criticality analysis. The benchmark description includes the material atom densities and other relevant parameters for cross section studies. This paper describes a whole-core, three-dimensional, code-to-code benchmark problem based on the European Pressurized Reactor (EPR) developed by AREVA NP. The core specifications were taken directly from the Final Safety Analysis Report (FSAR) submitted to the Nuclear Regulatory Commission (NRC) and the reactor core was modeled in a stylized manner while maintaining full heterogeneity at the pin and assembly level. Three different fresh core control rod configurations are presented in this paper – All Rods Out (ARO), Some Rods In (SRI), and All Rods In (ARI). Detailed Monte Carlo results are presented and include core eigenvalues, pin fission densities, and assembly averaged fission distributions. The benchmark results together with the provided macroscopic cross section libraries are useful for testing the numerical accuracy of transport solution methods for criticality analysis. The benchmark description includes the material atom densities and other relevant parameters for cross section studies. EPR Elsevier Benchmark Elsevier PWR Elsevier Rahnema, Farzad oth Enthalten in Elsevier Science Meyers, Carina Mello Guimaraes ELSEVIER Histone deacetylase 5 is a phosphorylation substrate of protein kinase D in osteoclasts 2022 the international review journal covering all aspects of nuclear energy Amsterdam [u.a.] (DE-627)ELV007755775 volume:93 year:2016 pages:18-46 extent:29 https://doi.org/10.1016/j.pnucene.2016.07.009 Volltext GBV_USEFLAG_U GBV_ELV SYSFLAG_U SSG-OLC-PHA 44.83 Rheumatologie Orthopädie VZ AR 93 2016 18-46 29 045F 620 |
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10.1016/j.pnucene.2016.07.009 doi GBVA2016004000014.pica (DE-627)ELV035087269 (ELSEVIER)S0149-1970(16)30152-4 DE-627 ger DE-627 rakwb eng 620 620 DE-600 610 VZ 44.83 bkl Lago, Daniel verfasserin aut Benchmark description of a stylized three-dimensional European Pressurized Reactor (EPR) problem 2016transfer abstract 29 nicht spezifiziert zzz rdacontent nicht spezifiziert z rdamedia nicht spezifiziert zu rdacarrier This paper describes a whole-core, three-dimensional, code-to-code benchmark problem based on the European Pressurized Reactor (EPR) developed by AREVA NP. The core specifications were taken directly from the Final Safety Analysis Report (FSAR) submitted to the Nuclear Regulatory Commission (NRC) and the reactor core was modeled in a stylized manner while maintaining full heterogeneity at the pin and assembly level. Three different fresh core control rod configurations are presented in this paper – All Rods Out (ARO), Some Rods In (SRI), and All Rods In (ARI). Detailed Monte Carlo results are presented and include core eigenvalues, pin fission densities, and assembly averaged fission distributions. The benchmark results together with the provided macroscopic cross section libraries are useful for testing the numerical accuracy of transport solution methods for criticality analysis. The benchmark description includes the material atom densities and other relevant parameters for cross section studies. This paper describes a whole-core, three-dimensional, code-to-code benchmark problem based on the European Pressurized Reactor (EPR) developed by AREVA NP. The core specifications were taken directly from the Final Safety Analysis Report (FSAR) submitted to the Nuclear Regulatory Commission (NRC) and the reactor core was modeled in a stylized manner while maintaining full heterogeneity at the pin and assembly level. Three different fresh core control rod configurations are presented in this paper – All Rods Out (ARO), Some Rods In (SRI), and All Rods In (ARI). Detailed Monte Carlo results are presented and include core eigenvalues, pin fission densities, and assembly averaged fission distributions. The benchmark results together with the provided macroscopic cross section libraries are useful for testing the numerical accuracy of transport solution methods for criticality analysis. The benchmark description includes the material atom densities and other relevant parameters for cross section studies. EPR Elsevier Benchmark Elsevier PWR Elsevier Rahnema, Farzad oth Enthalten in Elsevier Science Meyers, Carina Mello Guimaraes ELSEVIER Histone deacetylase 5 is a phosphorylation substrate of protein kinase D in osteoclasts 2022 the international review journal covering all aspects of nuclear energy Amsterdam [u.a.] (DE-627)ELV007755775 volume:93 year:2016 pages:18-46 extent:29 https://doi.org/10.1016/j.pnucene.2016.07.009 Volltext GBV_USEFLAG_U GBV_ELV SYSFLAG_U SSG-OLC-PHA 44.83 Rheumatologie Orthopädie VZ AR 93 2016 18-46 29 045F 620 |
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10.1016/j.pnucene.2016.07.009 doi GBVA2016004000014.pica (DE-627)ELV035087269 (ELSEVIER)S0149-1970(16)30152-4 DE-627 ger DE-627 rakwb eng 620 620 DE-600 610 VZ 44.83 bkl Lago, Daniel verfasserin aut Benchmark description of a stylized three-dimensional European Pressurized Reactor (EPR) problem 2016transfer abstract 29 nicht spezifiziert zzz rdacontent nicht spezifiziert z rdamedia nicht spezifiziert zu rdacarrier This paper describes a whole-core, three-dimensional, code-to-code benchmark problem based on the European Pressurized Reactor (EPR) developed by AREVA NP. The core specifications were taken directly from the Final Safety Analysis Report (FSAR) submitted to the Nuclear Regulatory Commission (NRC) and the reactor core was modeled in a stylized manner while maintaining full heterogeneity at the pin and assembly level. Three different fresh core control rod configurations are presented in this paper – All Rods Out (ARO), Some Rods In (SRI), and All Rods In (ARI). Detailed Monte Carlo results are presented and include core eigenvalues, pin fission densities, and assembly averaged fission distributions. The benchmark results together with the provided macroscopic cross section libraries are useful for testing the numerical accuracy of transport solution methods for criticality analysis. The benchmark description includes the material atom densities and other relevant parameters for cross section studies. This paper describes a whole-core, three-dimensional, code-to-code benchmark problem based on the European Pressurized Reactor (EPR) developed by AREVA NP. The core specifications were taken directly from the Final Safety Analysis Report (FSAR) submitted to the Nuclear Regulatory Commission (NRC) and the reactor core was modeled in a stylized manner while maintaining full heterogeneity at the pin and assembly level. Three different fresh core control rod configurations are presented in this paper – All Rods Out (ARO), Some Rods In (SRI), and All Rods In (ARI). Detailed Monte Carlo results are presented and include core eigenvalues, pin fission densities, and assembly averaged fission distributions. The benchmark results together with the provided macroscopic cross section libraries are useful for testing the numerical accuracy of transport solution methods for criticality analysis. The benchmark description includes the material atom densities and other relevant parameters for cross section studies. EPR Elsevier Benchmark Elsevier PWR Elsevier Rahnema, Farzad oth Enthalten in Elsevier Science Meyers, Carina Mello Guimaraes ELSEVIER Histone deacetylase 5 is a phosphorylation substrate of protein kinase D in osteoclasts 2022 the international review journal covering all aspects of nuclear energy Amsterdam [u.a.] (DE-627)ELV007755775 volume:93 year:2016 pages:18-46 extent:29 https://doi.org/10.1016/j.pnucene.2016.07.009 Volltext GBV_USEFLAG_U GBV_ELV SYSFLAG_U SSG-OLC-PHA 44.83 Rheumatologie Orthopädie VZ AR 93 2016 18-46 29 045F 620 |
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10.1016/j.pnucene.2016.07.009 doi GBVA2016004000014.pica (DE-627)ELV035087269 (ELSEVIER)S0149-1970(16)30152-4 DE-627 ger DE-627 rakwb eng 620 620 DE-600 610 VZ 44.83 bkl Lago, Daniel verfasserin aut Benchmark description of a stylized three-dimensional European Pressurized Reactor (EPR) problem 2016transfer abstract 29 nicht spezifiziert zzz rdacontent nicht spezifiziert z rdamedia nicht spezifiziert zu rdacarrier This paper describes a whole-core, three-dimensional, code-to-code benchmark problem based on the European Pressurized Reactor (EPR) developed by AREVA NP. The core specifications were taken directly from the Final Safety Analysis Report (FSAR) submitted to the Nuclear Regulatory Commission (NRC) and the reactor core was modeled in a stylized manner while maintaining full heterogeneity at the pin and assembly level. Three different fresh core control rod configurations are presented in this paper – All Rods Out (ARO), Some Rods In (SRI), and All Rods In (ARI). Detailed Monte Carlo results are presented and include core eigenvalues, pin fission densities, and assembly averaged fission distributions. The benchmark results together with the provided macroscopic cross section libraries are useful for testing the numerical accuracy of transport solution methods for criticality analysis. The benchmark description includes the material atom densities and other relevant parameters for cross section studies. This paper describes a whole-core, three-dimensional, code-to-code benchmark problem based on the European Pressurized Reactor (EPR) developed by AREVA NP. The core specifications were taken directly from the Final Safety Analysis Report (FSAR) submitted to the Nuclear Regulatory Commission (NRC) and the reactor core was modeled in a stylized manner while maintaining full heterogeneity at the pin and assembly level. Three different fresh core control rod configurations are presented in this paper – All Rods Out (ARO), Some Rods In (SRI), and All Rods In (ARI). Detailed Monte Carlo results are presented and include core eigenvalues, pin fission densities, and assembly averaged fission distributions. The benchmark results together with the provided macroscopic cross section libraries are useful for testing the numerical accuracy of transport solution methods for criticality analysis. The benchmark description includes the material atom densities and other relevant parameters for cross section studies. EPR Elsevier Benchmark Elsevier PWR Elsevier Rahnema, Farzad oth Enthalten in Elsevier Science Meyers, Carina Mello Guimaraes ELSEVIER Histone deacetylase 5 is a phosphorylation substrate of protein kinase D in osteoclasts 2022 the international review journal covering all aspects of nuclear energy Amsterdam [u.a.] (DE-627)ELV007755775 volume:93 year:2016 pages:18-46 extent:29 https://doi.org/10.1016/j.pnucene.2016.07.009 Volltext GBV_USEFLAG_U GBV_ELV SYSFLAG_U SSG-OLC-PHA 44.83 Rheumatologie Orthopädie VZ AR 93 2016 18-46 29 045F 620 |
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Histone deacetylase 5 is a phosphorylation substrate of protein kinase D in osteoclasts |
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Histone deacetylase 5 is a phosphorylation substrate of protein kinase D in osteoclasts |
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Benchmark description of a stylized three-dimensional European Pressurized Reactor (EPR) problem |
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Benchmark description of a stylized three-dimensional European Pressurized Reactor (EPR) problem |
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Lago, Daniel |
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Histone deacetylase 5 is a phosphorylation substrate of protein kinase D in osteoclasts |
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benchmark description of a stylized three-dimensional european pressurized reactor (epr) problem |
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Benchmark description of a stylized three-dimensional European Pressurized Reactor (EPR) problem |
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This paper describes a whole-core, three-dimensional, code-to-code benchmark problem based on the European Pressurized Reactor (EPR) developed by AREVA NP. The core specifications were taken directly from the Final Safety Analysis Report (FSAR) submitted to the Nuclear Regulatory Commission (NRC) and the reactor core was modeled in a stylized manner while maintaining full heterogeneity at the pin and assembly level. Three different fresh core control rod configurations are presented in this paper – All Rods Out (ARO), Some Rods In (SRI), and All Rods In (ARI). Detailed Monte Carlo results are presented and include core eigenvalues, pin fission densities, and assembly averaged fission distributions. The benchmark results together with the provided macroscopic cross section libraries are useful for testing the numerical accuracy of transport solution methods for criticality analysis. The benchmark description includes the material atom densities and other relevant parameters for cross section studies. |
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This paper describes a whole-core, three-dimensional, code-to-code benchmark problem based on the European Pressurized Reactor (EPR) developed by AREVA NP. The core specifications were taken directly from the Final Safety Analysis Report (FSAR) submitted to the Nuclear Regulatory Commission (NRC) and the reactor core was modeled in a stylized manner while maintaining full heterogeneity at the pin and assembly level. Three different fresh core control rod configurations are presented in this paper – All Rods Out (ARO), Some Rods In (SRI), and All Rods In (ARI). Detailed Monte Carlo results are presented and include core eigenvalues, pin fission densities, and assembly averaged fission distributions. The benchmark results together with the provided macroscopic cross section libraries are useful for testing the numerical accuracy of transport solution methods for criticality analysis. The benchmark description includes the material atom densities and other relevant parameters for cross section studies. |
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This paper describes a whole-core, three-dimensional, code-to-code benchmark problem based on the European Pressurized Reactor (EPR) developed by AREVA NP. The core specifications were taken directly from the Final Safety Analysis Report (FSAR) submitted to the Nuclear Regulatory Commission (NRC) and the reactor core was modeled in a stylized manner while maintaining full heterogeneity at the pin and assembly level. Three different fresh core control rod configurations are presented in this paper – All Rods Out (ARO), Some Rods In (SRI), and All Rods In (ARI). Detailed Monte Carlo results are presented and include core eigenvalues, pin fission densities, and assembly averaged fission distributions. The benchmark results together with the provided macroscopic cross section libraries are useful for testing the numerical accuracy of transport solution methods for criticality analysis. The benchmark description includes the material atom densities and other relevant parameters for cross section studies. |
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Benchmark description of a stylized three-dimensional European Pressurized Reactor (EPR) problem |
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