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Propagation of nuclear data uncertainties in fuel cycle calculations using MONTE-CARLO Technique
Cita
Cabellos de Francisco, Oscar Luis 
ORCID: https://orcid.org/0000-0002-2684-280X, Diez de la Obra, Carlos Javier and Martínez, J.S.
(2011).
Propagation of nuclear data uncertainties in fuel cycle calculations using MONTE-CARLO Technique.
En: "International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering, M&C 2011", 08/05/2011 - 12/05/2011, Río de Janeiro, Brasil. pp. 1-4.
ORCID: https://orcid.org/0000-0002-2684-280X, Diez de la Obra, Carlos Javier and Martínez, J.S.
(2011).
Propagation of nuclear data uncertainties in fuel cycle calculations using MONTE-CARLO Technique.
En: "International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering, M&C 2011", 08/05/2011 - 12/05/2011, Río de Janeiro, Brasil. pp. 1-4.
Descripción
| Título: | Propagation of nuclear data uncertainties in fuel cycle calculations using MONTE-CARLO Technique |
|---|---|
| Autor/es: |
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| Tipo de Documento: | Ponencia en Congreso o Jornada (Artículo) |
| Título del Evento: | International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering, M&C 2011 |
| Fechas del Evento: | 08/05/2011 - 12/05/2011 |
| Lugar del Evento: | Río de Janeiro, Brasil |
| Título del Libro: | Proceedings of the International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2011) |
| Fecha: | 2011 |
| Materias: | |
| ODS: | |
| Escuela: | E.T.S.I. Industriales (UPM) |
| Departamento: | Ingeniería Nuclear [hasta 2014] |
| Licencias Creative Commons: | Reconocimiento - Sin obra derivada - No comercial |
Resumen
The uncertainty propagation in fuel cycle calculations due to Nuclear Data (ND) is a important important issue for : issue for :
• Present fuel cycles (e.g. high burnup fuel programme)
• New fuel cycles designs (e.g. fast breeder reactors and ADS)
Different error propagation techniques can be used:
• Sensitivity analysis
• Response Response Surface Method Surface Method
• Monte Carlo technique
Then, p p , , in this paper, it is assessed the imp y pact of ND uncertainties on the decay heat and radiotoxicity in two applications:
• Fission Pulse Decay ( y Heat calculation (FPDH)
• Conceptual design of European Facility for Industrial Transmutation (EFIT)
Más información
| ID de Registro: | 11575 |
|---|---|
| Identificador DC: | https://oa.upm.es/11575/ |
| Identificador OAI: | oai:oa.upm.es:11575 |
| URL Oficial: | http://www.tdn.com.br/mc2011/ |
| Depositado por: | Memoria Investigacion |
| Depositado el: | 18 Jul 2012 11:04 |
| Ultima Modificación: | 03 Mar 2023 09:31 |
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