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Application of the Monte Carlo method to estimate doses due to neutron activation of different materials in a nuclear reactor

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Application of the Monte Carlo method to estimate doses due to neutron activation of different materials in a nuclear reactor

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dc.contributor.author Ródenas Diago, José es_ES
dc.date.accessioned 2018-07-09T06:58:10Z
dc.date.available 2018-07-09T06:58:10Z
dc.date.issued 2017 es_ES
dc.identifier.issn 0969-806X es_ES
dc.identifier.uri http://hdl.handle.net/10251/105553
dc.description.abstract [EN] All materials exposed to some neutron flux can be activated independently of the kind of the neutron source. In this study, a nuclear reactor has been considered as neutron source. In particular, the activation of control rods in a BWR is studied to obtain the doses produced around the storage pool for irradiated fuel of the plant when control rods are withdrawn from the reactor and installed into this pool. It is very important to calculate these doses because they can affect to plant workers in the area. The MCNP code based on the Monte Carlo method has been applied to simulate activation reactions produced in the control rods inserted into the reactor. Obtained activities are introduced as input into another MC model to estimate doses produced by them. The comparison of simulation results with experimental measurements allows the validation of developed models. The developed MC models have been also applied to simulate the activation of other materials, such as components of a stainless steel sample introduced into a training reactors. These models, once validated, can be applied to other situations and materials where a neutron flux can be found, not only nuclear reactors. For instance, activation analysis with an Am-Be source, neutrography techniques in both medical applications and non-destructive analysis of materials, civil engineering applications using a Troxler, analysis of materials in decommissioning of nuclear power plants, etc. es_ES
dc.language Inglés es_ES
dc.publisher Elsevier es_ES
dc.relation.ispartof Radiation Physics and Chemistry es_ES
dc.rights Reconocimiento - No comercial - Sin obra derivada (by-nc-nd) es_ES
dc.subject Monte Carlo method es_ES
dc.subject Dose estimation es_ES
dc.subject Neutron activation es_ES
dc.subject.classification INGENIERIA NUCLEAR es_ES
dc.title Application of the Monte Carlo method to estimate doses due to neutron activation of different materials in a nuclear reactor es_ES
dc.type Artículo es_ES
dc.type Comunicación en congreso es_ES
dc.identifier.doi 10.1016/j.radphyschem.2017.02.015 es_ES
dc.rights.accessRights Abierto es_ES
dc.contributor.affiliation Universitat Politècnica de València. Departamento de Ingeniería Química y Nuclear - Departament d'Enginyeria Química i Nuclear es_ES
dc.description.bibliographicCitation Ródenas Diago, J. (2017). Application of the Monte Carlo method to estimate doses due to neutron activation of different materials in a nuclear reactor. Radiation Physics and Chemistry. 140:442-446. doi:10.1016/j.radphyschem.2017.02.015 es_ES
dc.description.accrualMethod S es_ES
dc.relation.conferencename 2nd International Conference on Dosimetry and its Applications (ICDA-2) es_ES
dc.relation.conferencedate July 03-08,2016 es_ES
dc.relation.conferenceplace Guildford, UK es_ES
dc.relation.publisherversion http://dx.doi.org/10.1016/j.radphyschem.2017.02.015 es_ES
dc.description.upvformatpinicio 442 es_ES
dc.description.upvformatpfin 446 es_ES
dc.type.version info:eu-repo/semantics/publishedVersion es_ES
dc.description.volume 140 es_ES
dc.relation.pasarela S\360275 es_ES


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