Neutron-induced nuclear data for the MYRRHA fast spectrum facility

Romojaro Otero, Pablo; Zerovnik, Gasper; Álvarez-Velarde, Francisco; Stankovskiy, Alexey; Kodeli, I.; Fiorito, Luca; Díez, Carlos Javier; Cabellos de Francisco, Oscar Luis; García Herranz, Nuria; Heyse, Jan; Paradela, Carlos; Schillebeeckx, Peter y Van den Eynde, Gert (2017). Neutron-induced nuclear data for the MYRRHA fast spectrum facility. "EPJ Web of Conferences", v. 146 (n. 09007); pp. 1-4. ISSN 2100-014X. https://doi.org/10.1051/epjconf/201714609007.

Descripción

Título: Neutron-induced nuclear data for the MYRRHA fast spectrum facility
Autor/es:
  • Romojaro Otero, Pablo
  • Zerovnik, Gasper
  • Álvarez-Velarde, Francisco
  • Stankovskiy, Alexey
  • Kodeli, I.
  • Fiorito, Luca
  • Díez, Carlos Javier
  • Cabellos de Francisco, Oscar Luis
  • García Herranz, Nuria
  • Heyse, Jan
  • Paradela, Carlos
  • Schillebeeckx, Peter
  • Van den Eynde, Gert
Tipo de Documento: Artículo
Título del Evento: EPJ Web of conferences 146, 09007 (2017)
Lugar del Evento: Brujas
Título de Revista/Publicación: EPJ Web of Conferences
Fecha: 2017
Volumen: 146
Materias:
Escuela: E.T.S.I. Industriales (UPM)
Departamento: Ingeniería Energética
Licencias Creative Commons: Reconocimiento - Sin obra derivada - No comercial

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Resumen

The MYRRHA (Multi-purpose hYbrid Research Reactor for High-tech Applications) concept is a flexible experimental lead-bismuth cooled and mixed-oxide (MOX) fueled fast spectrum facility designed to operate both in sub-critical (accelerator driven) and critical modes. One of the key issues for the safe operation of the reactor is the uncertainty assessment during the design works. The main objective of the European project CHANDA (solving CHAllenges in Nuclear DAta) Work Package 10 is to improve MYRRHA relevant nuclear data in order to reduce the reactor parameter uncertainties derived from them. In order to achieve this goal, several tasks have been undertaken. First, a sensitivity study of MYRRHA integral parameters, such as energy dependent cross sections, fission spectra and neutron multiplicities, to nuclear data has been conducted resulting in a list of MYRRHA relevant quantities (nuclides and reactions). On the second task, an analysis of the existing experimental data and evaluations for the quantities included in the list has been carried out. In this framework, the impact on the multiplication factor of quantities from different nuclear data libraries for different nuclides, reactions and energy regions has been investigated on the MYRRHA MOX critical core model. As the next step, new experiments and evaluations will be performed in order to improve existing nuclear data libraries.

Proyectos asociados

TipoCódigoAcrónimoResponsableTítulo
FP7605203CHANDASin especificarSolving CHAllenges in Nuclear DAta

Más información

ID de Registro: 49978
Identificador DC: http://oa.upm.es/49978/
Identificador OAI: oai:oa.upm.es:49978
Identificador DOI: 10.1051/epjconf/201714609007
URL Oficial: https://www.epj-conferences.org/articles/epjconf/abs/2017/15/epjconf-nd2016_09007/epjconf-nd2016_09007.html
Depositado por: Memoria Investigacion
Depositado el: 08 Jun 2018 16:10
Ultima Modificación: 08 Jun 2018 16:10
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