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Assessment of fissionable material behaviour in fission chambers
Cita
Cabellos de Francisco, Oscar Luis 
ORCID: https://orcid.org/0000-0002-2684-280X, Fernandez, Patricia, Rapisarda, D. and García Herranz, Nuria ORCID: https://orcid.org/0000-0002-0760-2974
(2010).
Assessment of fissionable material behaviour in fission chambers.
"Nuclear Instruments and Methods in Physics Research A", v. 618
(n. 1-3);
pp. 248-259.
ISSN 0168-9002.
https://doi.org/10.1016/j.nima.2010.02.114.
ORCID: https://orcid.org/0000-0002-2684-280X, Fernandez, Patricia, Rapisarda, D. and García Herranz, Nuria ORCID: https://orcid.org/0000-0002-0760-2974
(2010).
Assessment of fissionable material behaviour in fission chambers.
"Nuclear Instruments and Methods in Physics Research A", v. 618
(n. 1-3);
pp. 248-259.
ISSN 0168-9002.
https://doi.org/10.1016/j.nima.2010.02.114.
Descripción
| Título: | Assessment of fissionable material behaviour in fission chambers |
|---|---|
| Autor/es: |
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| Tipo de Documento: | Artículo |
| Título de Revista/Publicación: | Nuclear Instruments and Methods in Physics Research A |
| Fecha: | Enero 2010 |
| ISSN: | 0168-9002 |
| Volumen: | 618 |
| Número: | 1-3 |
| Materias: | |
| ODS: | |
| Palabras Clave Informales: | Fission chamber; BR2; DEMO; IFMIF; Uncertainty cross-sections |
| Escuela: | E.T.S.I. Industriales (UPM) |
| Departamento: | Ingeniería Nuclear [hasta 2014] |
| Licencias Creative Commons: | Reconocimiento - Sin obra derivada - No comercial |
Resumen
A comprehensive study is performed in order to assess the pertinence of fission chambers coated with different fissile materials for high neutron flux detection. Three neutron scenarios are proposed to study the fast component of a high neutron flux: (i) high neutron flux with a significant thermal contribution such as BR2, (ii) DEMO magnetic fusion reactor, and (iii) IFMIF high flux test module.
In this study, the inventory code ACAB is used to analyze the following questions: (i) impact of different deposits in fission chambers; (ii) effect of the irradiation time/burn-up on the concentration; (iii) impact of activation cross-section uncertainties on the composition of the deposit for all the range of burn-up/irradiation neutron fluences of interest. The complete set of nuclear data (decay, fission yield, activation cross-sections, and uncertainties) provided in the EAF2007 data library are used for this evaluation.
Más información
| ID de Registro: | 6718 |
|---|---|
| Identificador DC: | https://oa.upm.es/6718/ |
| Identificador OAI: | oai:oa.upm.es:6718 |
| URL Portal Científico: | https://portalcientifico.upm.es/es/ipublic/item/5484949 |
| Identificador DOI: | 10.1016/j.nima.2010.02.114 |
| URL Oficial: | http://www.sciencedirect.com/science/journal/01689... |
| Depositado por: | Memoria Investigacion |
| Depositado el: | 27 Abr 2011 11:51 |
| Ultima Modificación: | 12 Nov 2025 00:00 |
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