Spanish contribution to the development and application of best estimate plus uncertainty methodologies: Past, present and future
Best-Estimate Plus Uncertainty (BEPU) nuclear safety analysis is an approach widely used in the field of nuclear engineering and reactor safety assessment. It aims to provide a more realistic assessment of reactor safety by considering a combination of best-estimate models and the quantification of...
Ausführliche Beschreibung
Gespeichert in:
| Autor*in: |
Freixa, J. [verfasserIn] Barrachina, T. [verfasserIn] Berna, C. [verfasserIn] Bocanegra, R. [verfasserIn] Carlos, S. [verfasserIn] Castro, E. [verfasserIn] Cuervo, D. [verfasserIn] Durán-Vinuesa, L.F. [verfasserIn] Escrivá, A. [verfasserIn] Feria, F. [verfasserIn] Cosials, K. Fernández [verfasserIn] García-Herranz, N. [verfasserIn] Herranz, L.E. [verfasserIn] Jiménez, G. [verfasserIn] Martínez-Quiroga, V. [verfasserIn] Martorell, S. [verfasserIn] Mendizabal, R. [verfasserIn] Miró, R. [verfasserIn] Muñoz-Cobo, J.L. [verfasserIn] Pérez-Ferragut, M. [verfasserIn] Pericas, R. [verfasserIn] Queral, C. [verfasserIn] Reventós, F. [verfasserIn] Riverola, J. [verfasserIn] Sánchez, A. [verfasserIn] Villanueva, J.F. [verfasserIn] |
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| Format: |
E-Artikel |
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| Sprache: |
Englisch |
| Erschienen: |
2023 |
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| Schlagwörter: |
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| Übergeordnetes Werk: |
Enthalten in: Nuclear engineering and design - Amsterdam [u.a.] : Elsevier Science, 1966, 417 |
|---|---|
| Übergeordnetes Werk: |
volume:417 |
| DOI / URN: |
10.1016/j.nucengdes.2023.112837 |
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| Katalog-ID: |
ELV066633885 |
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| 520 | |a Best-Estimate Plus Uncertainty (BEPU) nuclear safety analysis is an approach widely used in the field of nuclear engineering and reactor safety assessment. It aims to provide a more realistic assessment of reactor safety by considering a combination of best-estimate models and the quantification of the uncertainty of the input and code data. | ||
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| 700 | 1 | |a Berna, C. |e verfasserin |4 aut | |
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| 700 | 1 | |a Carlos, S. |e verfasserin |4 aut | |
| 700 | 1 | |a Castro, E. |e verfasserin |4 aut | |
| 700 | 1 | |a Cuervo, D. |e verfasserin |4 aut | |
| 700 | 1 | |a Durán-Vinuesa, L.F. |e verfasserin |4 aut | |
| 700 | 1 | |a Escrivá, A. |e verfasserin |4 aut | |
| 700 | 1 | |a Feria, F. |e verfasserin |4 aut | |
| 700 | 1 | |a Cosials, K. Fernández |e verfasserin |4 aut | |
| 700 | 1 | |a García-Herranz, N. |e verfasserin |4 aut | |
| 700 | 1 | |a Herranz, L.E. |e verfasserin |4 aut | |
| 700 | 1 | |a Jiménez, G. |e verfasserin |4 aut | |
| 700 | 1 | |a Martínez-Quiroga, V. |e verfasserin |4 aut | |
| 700 | 1 | |a Martorell, S. |e verfasserin |4 aut | |
| 700 | 1 | |a Mendizabal, R. |e verfasserin |4 aut | |
| 700 | 1 | |a Miró, R. |e verfasserin |4 aut | |
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| 700 | 1 | |a Queral, C. |e verfasserin |4 aut | |
| 700 | 1 | |a Reventós, F. |e verfasserin |4 aut | |
| 700 | 1 | |a Riverola, J. |e verfasserin |4 aut | |
| 700 | 1 | |a Sánchez, A. |e verfasserin |4 aut | |
| 700 | 1 | |a Villanueva, J.F. |e verfasserin |4 aut | |
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10.1016/j.nucengdes.2023.112837 doi (DE-627)ELV066633885 (ELSEVIER)S0029-5493(23)00686-6 DE-627 ger DE-627 rda eng 620 VZ 52.55 bkl Freixa, J. verfasserin (orcid)0000-0002-8173-3921 aut Spanish contribution to the development and application of best estimate plus uncertainty methodologies: Past, present and future 2023 nicht spezifiziert zzz rdacontent Computermedien c rdamedia Online-Ressource cr rdacarrier Best-Estimate Plus Uncertainty (BEPU) nuclear safety analysis is an approach widely used in the field of nuclear engineering and reactor safety assessment. It aims to provide a more realistic assessment of reactor safety by considering a combination of best-estimate models and the quantification of the uncertainty of the input and code data. BEPU Uncertainty Safety analysis Barrachina, T. verfasserin aut Berna, C. verfasserin aut Bocanegra, R. verfasserin aut Carlos, S. verfasserin aut Castro, E. verfasserin aut Cuervo, D. verfasserin aut Durán-Vinuesa, L.F. verfasserin aut Escrivá, A. verfasserin aut Feria, F. verfasserin aut Cosials, K. Fernández verfasserin aut García-Herranz, N. verfasserin aut Herranz, L.E. verfasserin aut Jiménez, G. verfasserin aut Martínez-Quiroga, V. verfasserin aut Martorell, S. verfasserin aut Mendizabal, R. verfasserin aut Miró, R. verfasserin aut Muñoz-Cobo, J.L. verfasserin aut Pérez-Ferragut, M. verfasserin aut Pericas, R. verfasserin aut Queral, C. verfasserin aut Reventós, F. verfasserin aut Riverola, J. verfasserin aut Sánchez, A. verfasserin aut Villanueva, J.F. verfasserin aut Enthalten in Nuclear engineering and design Amsterdam [u.a.] : Elsevier Science, 1966 417 Online-Ressource (DE-627)320411087 (DE-600)2001319-X (DE-576)251938182 0029-5493 nnns volume:417 GBV_USEFLAG_U GBV_ELV SYSFLAG_U GBV_ILN_20 GBV_ILN_22 GBV_ILN_23 GBV_ILN_24 GBV_ILN_31 GBV_ILN_32 GBV_ILN_40 GBV_ILN_60 GBV_ILN_62 GBV_ILN_65 GBV_ILN_69 GBV_ILN_70 GBV_ILN_73 GBV_ILN_74 GBV_ILN_90 GBV_ILN_95 GBV_ILN_100 GBV_ILN_105 GBV_ILN_110 GBV_ILN_150 GBV_ILN_151 GBV_ILN_187 GBV_ILN_213 GBV_ILN_224 GBV_ILN_230 GBV_ILN_370 GBV_ILN_602 GBV_ILN_702 GBV_ILN_2001 GBV_ILN_2003 GBV_ILN_2004 GBV_ILN_2005 GBV_ILN_2007 GBV_ILN_2008 GBV_ILN_2009 GBV_ILN_2010 GBV_ILN_2011 GBV_ILN_2014 GBV_ILN_2015 GBV_ILN_2020 GBV_ILN_2021 GBV_ILN_2025 GBV_ILN_2026 GBV_ILN_2027 GBV_ILN_2034 GBV_ILN_2044 GBV_ILN_2048 GBV_ILN_2049 GBV_ILN_2050 GBV_ILN_2055 GBV_ILN_2056 GBV_ILN_2059 GBV_ILN_2061 GBV_ILN_2064 GBV_ILN_2088 GBV_ILN_2106 GBV_ILN_2110 GBV_ILN_2111 GBV_ILN_2112 GBV_ILN_2122 GBV_ILN_2129 GBV_ILN_2143 GBV_ILN_2152 GBV_ILN_2153 GBV_ILN_2190 GBV_ILN_2232 GBV_ILN_2336 GBV_ILN_2470 GBV_ILN_2507 GBV_ILN_4035 GBV_ILN_4037 GBV_ILN_4112 GBV_ILN_4125 GBV_ILN_4242 GBV_ILN_4249 GBV_ILN_4251 GBV_ILN_4305 GBV_ILN_4306 GBV_ILN_4307 GBV_ILN_4313 GBV_ILN_4322 GBV_ILN_4323 GBV_ILN_4324 GBV_ILN_4325 GBV_ILN_4326 GBV_ILN_4333 GBV_ILN_4334 GBV_ILN_4338 GBV_ILN_4393 GBV_ILN_4700 52.55 Kerntechnik Reaktortechnik VZ AR 417 |
| spelling |
10.1016/j.nucengdes.2023.112837 doi (DE-627)ELV066633885 (ELSEVIER)S0029-5493(23)00686-6 DE-627 ger DE-627 rda eng 620 VZ 52.55 bkl Freixa, J. verfasserin (orcid)0000-0002-8173-3921 aut Spanish contribution to the development and application of best estimate plus uncertainty methodologies: Past, present and future 2023 nicht spezifiziert zzz rdacontent Computermedien c rdamedia Online-Ressource cr rdacarrier Best-Estimate Plus Uncertainty (BEPU) nuclear safety analysis is an approach widely used in the field of nuclear engineering and reactor safety assessment. It aims to provide a more realistic assessment of reactor safety by considering a combination of best-estimate models and the quantification of the uncertainty of the input and code data. BEPU Uncertainty Safety analysis Barrachina, T. verfasserin aut Berna, C. verfasserin aut Bocanegra, R. verfasserin aut Carlos, S. verfasserin aut Castro, E. verfasserin aut Cuervo, D. verfasserin aut Durán-Vinuesa, L.F. verfasserin aut Escrivá, A. verfasserin aut Feria, F. verfasserin aut Cosials, K. Fernández verfasserin aut García-Herranz, N. verfasserin aut Herranz, L.E. verfasserin aut Jiménez, G. verfasserin aut Martínez-Quiroga, V. verfasserin aut Martorell, S. verfasserin aut Mendizabal, R. verfasserin aut Miró, R. verfasserin aut Muñoz-Cobo, J.L. verfasserin aut Pérez-Ferragut, M. verfasserin aut Pericas, R. verfasserin aut Queral, C. verfasserin aut Reventós, F. verfasserin aut Riverola, J. verfasserin aut Sánchez, A. verfasserin aut Villanueva, J.F. verfasserin aut Enthalten in Nuclear engineering and design Amsterdam [u.a.] : Elsevier Science, 1966 417 Online-Ressource (DE-627)320411087 (DE-600)2001319-X (DE-576)251938182 0029-5493 nnns volume:417 GBV_USEFLAG_U GBV_ELV SYSFLAG_U GBV_ILN_20 GBV_ILN_22 GBV_ILN_23 GBV_ILN_24 GBV_ILN_31 GBV_ILN_32 GBV_ILN_40 GBV_ILN_60 GBV_ILN_62 GBV_ILN_65 GBV_ILN_69 GBV_ILN_70 GBV_ILN_73 GBV_ILN_74 GBV_ILN_90 GBV_ILN_95 GBV_ILN_100 GBV_ILN_105 GBV_ILN_110 GBV_ILN_150 GBV_ILN_151 GBV_ILN_187 GBV_ILN_213 GBV_ILN_224 GBV_ILN_230 GBV_ILN_370 GBV_ILN_602 GBV_ILN_702 GBV_ILN_2001 GBV_ILN_2003 GBV_ILN_2004 GBV_ILN_2005 GBV_ILN_2007 GBV_ILN_2008 GBV_ILN_2009 GBV_ILN_2010 GBV_ILN_2011 GBV_ILN_2014 GBV_ILN_2015 GBV_ILN_2020 GBV_ILN_2021 GBV_ILN_2025 GBV_ILN_2026 GBV_ILN_2027 GBV_ILN_2034 GBV_ILN_2044 GBV_ILN_2048 GBV_ILN_2049 GBV_ILN_2050 GBV_ILN_2055 GBV_ILN_2056 GBV_ILN_2059 GBV_ILN_2061 GBV_ILN_2064 GBV_ILN_2088 GBV_ILN_2106 GBV_ILN_2110 GBV_ILN_2111 GBV_ILN_2112 GBV_ILN_2122 GBV_ILN_2129 GBV_ILN_2143 GBV_ILN_2152 GBV_ILN_2153 GBV_ILN_2190 GBV_ILN_2232 GBV_ILN_2336 GBV_ILN_2470 GBV_ILN_2507 GBV_ILN_4035 GBV_ILN_4037 GBV_ILN_4112 GBV_ILN_4125 GBV_ILN_4242 GBV_ILN_4249 GBV_ILN_4251 GBV_ILN_4305 GBV_ILN_4306 GBV_ILN_4307 GBV_ILN_4313 GBV_ILN_4322 GBV_ILN_4323 GBV_ILN_4324 GBV_ILN_4325 GBV_ILN_4326 GBV_ILN_4333 GBV_ILN_4334 GBV_ILN_4338 GBV_ILN_4393 GBV_ILN_4700 52.55 Kerntechnik Reaktortechnik VZ AR 417 |
| allfields_unstemmed |
10.1016/j.nucengdes.2023.112837 doi (DE-627)ELV066633885 (ELSEVIER)S0029-5493(23)00686-6 DE-627 ger DE-627 rda eng 620 VZ 52.55 bkl Freixa, J. verfasserin (orcid)0000-0002-8173-3921 aut Spanish contribution to the development and application of best estimate plus uncertainty methodologies: Past, present and future 2023 nicht spezifiziert zzz rdacontent Computermedien c rdamedia Online-Ressource cr rdacarrier Best-Estimate Plus Uncertainty (BEPU) nuclear safety analysis is an approach widely used in the field of nuclear engineering and reactor safety assessment. It aims to provide a more realistic assessment of reactor safety by considering a combination of best-estimate models and the quantification of the uncertainty of the input and code data. BEPU Uncertainty Safety analysis Barrachina, T. verfasserin aut Berna, C. verfasserin aut Bocanegra, R. verfasserin aut Carlos, S. verfasserin aut Castro, E. verfasserin aut Cuervo, D. verfasserin aut Durán-Vinuesa, L.F. verfasserin aut Escrivá, A. verfasserin aut Feria, F. verfasserin aut Cosials, K. Fernández verfasserin aut García-Herranz, N. verfasserin aut Herranz, L.E. verfasserin aut Jiménez, G. verfasserin aut Martínez-Quiroga, V. verfasserin aut Martorell, S. verfasserin aut Mendizabal, R. verfasserin aut Miró, R. verfasserin aut Muñoz-Cobo, J.L. verfasserin aut Pérez-Ferragut, M. verfasserin aut Pericas, R. verfasserin aut Queral, C. verfasserin aut Reventós, F. verfasserin aut Riverola, J. verfasserin aut Sánchez, A. verfasserin aut Villanueva, J.F. verfasserin aut Enthalten in Nuclear engineering and design Amsterdam [u.a.] : Elsevier Science, 1966 417 Online-Ressource (DE-627)320411087 (DE-600)2001319-X (DE-576)251938182 0029-5493 nnns volume:417 GBV_USEFLAG_U GBV_ELV SYSFLAG_U GBV_ILN_20 GBV_ILN_22 GBV_ILN_23 GBV_ILN_24 GBV_ILN_31 GBV_ILN_32 GBV_ILN_40 GBV_ILN_60 GBV_ILN_62 GBV_ILN_65 GBV_ILN_69 GBV_ILN_70 GBV_ILN_73 GBV_ILN_74 GBV_ILN_90 GBV_ILN_95 GBV_ILN_100 GBV_ILN_105 GBV_ILN_110 GBV_ILN_150 GBV_ILN_151 GBV_ILN_187 GBV_ILN_213 GBV_ILN_224 GBV_ILN_230 GBV_ILN_370 GBV_ILN_602 GBV_ILN_702 GBV_ILN_2001 GBV_ILN_2003 GBV_ILN_2004 GBV_ILN_2005 GBV_ILN_2007 GBV_ILN_2008 GBV_ILN_2009 GBV_ILN_2010 GBV_ILN_2011 GBV_ILN_2014 GBV_ILN_2015 GBV_ILN_2020 GBV_ILN_2021 GBV_ILN_2025 GBV_ILN_2026 GBV_ILN_2027 GBV_ILN_2034 GBV_ILN_2044 GBV_ILN_2048 GBV_ILN_2049 GBV_ILN_2050 GBV_ILN_2055 GBV_ILN_2056 GBV_ILN_2059 GBV_ILN_2061 GBV_ILN_2064 GBV_ILN_2088 GBV_ILN_2106 GBV_ILN_2110 GBV_ILN_2111 GBV_ILN_2112 GBV_ILN_2122 GBV_ILN_2129 GBV_ILN_2143 GBV_ILN_2152 GBV_ILN_2153 GBV_ILN_2190 GBV_ILN_2232 GBV_ILN_2336 GBV_ILN_2470 GBV_ILN_2507 GBV_ILN_4035 GBV_ILN_4037 GBV_ILN_4112 GBV_ILN_4125 GBV_ILN_4242 GBV_ILN_4249 GBV_ILN_4251 GBV_ILN_4305 GBV_ILN_4306 GBV_ILN_4307 GBV_ILN_4313 GBV_ILN_4322 GBV_ILN_4323 GBV_ILN_4324 GBV_ILN_4325 GBV_ILN_4326 GBV_ILN_4333 GBV_ILN_4334 GBV_ILN_4338 GBV_ILN_4393 GBV_ILN_4700 52.55 Kerntechnik Reaktortechnik VZ AR 417 |
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Freixa, J. @@aut@@ Barrachina, T. @@aut@@ Berna, C. @@aut@@ Bocanegra, R. @@aut@@ Carlos, S. @@aut@@ Castro, E. @@aut@@ Cuervo, D. @@aut@@ Durán-Vinuesa, L.F. @@aut@@ Escrivá, A. @@aut@@ Feria, F. @@aut@@ Cosials, K. Fernández @@aut@@ García-Herranz, N. @@aut@@ Herranz, L.E. @@aut@@ Jiménez, G. @@aut@@ Martínez-Quiroga, V. @@aut@@ Martorell, S. @@aut@@ Mendizabal, R. @@aut@@ Miró, R. @@aut@@ Muñoz-Cobo, J.L. @@aut@@ Pérez-Ferragut, M. @@aut@@ Pericas, R. @@aut@@ Queral, C. @@aut@@ Reventós, F. @@aut@@ Riverola, J. @@aut@@ Sánchez, A. @@aut@@ Villanueva, J.F. @@aut@@ |
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620 VZ 52.55 bkl Spanish contribution to the development and application of best estimate plus uncertainty methodologies: Past, present and future BEPU Uncertainty Safety analysis |
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Freixa, J. Barrachina, T. Berna, C. Bocanegra, R. Carlos, S. Castro, E. Cuervo, D. Durán-Vinuesa, L.F. Escrivá, A. Feria, F. Cosials, K. Fernández García-Herranz, N. Herranz, L.E. Jiménez, G. Martínez-Quiroga, V. Martorell, S. Mendizabal, R. Miró, R. Muñoz-Cobo, J.L. Pérez-Ferragut, M. Pericas, R. Queral, C. Reventós, F. Riverola, J. Sánchez, A. Villanueva, J.F. |
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spanish contribution to the development and application of best estimate plus uncertainty methodologies: past, present and future |
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Spanish contribution to the development and application of best estimate plus uncertainty methodologies: Past, present and future |
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Best-Estimate Plus Uncertainty (BEPU) nuclear safety analysis is an approach widely used in the field of nuclear engineering and reactor safety assessment. It aims to provide a more realistic assessment of reactor safety by considering a combination of best-estimate models and the quantification of the uncertainty of the input and code data. |
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Best-Estimate Plus Uncertainty (BEPU) nuclear safety analysis is an approach widely used in the field of nuclear engineering and reactor safety assessment. It aims to provide a more realistic assessment of reactor safety by considering a combination of best-estimate models and the quantification of the uncertainty of the input and code data. |
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Best-Estimate Plus Uncertainty (BEPU) nuclear safety analysis is an approach widely used in the field of nuclear engineering and reactor safety assessment. It aims to provide a more realistic assessment of reactor safety by considering a combination of best-estimate models and the quantification of the uncertainty of the input and code data. |
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| score |
7.401292 |