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Application of dosimetry measurements to analyze the neutron activation of a stainless steel sample in a training nuclear reactor

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Application of dosimetry measurements to analyze the neutron activation of a stainless steel sample in a training nuclear reactor

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dc.contributor.author Ródenas Diago, José es_ES
dc.contributor.author Gallardo Bermell, Sergio es_ES
dc.contributor.author Weirich, F. es_ES
dc.contributor.author Hansen, W. es_ES
dc.date.accessioned 2015-05-08T11:35:01Z
dc.date.available 2015-05-08T11:35:01Z
dc.date.issued 2014-11
dc.identifier.issn 0969-806X
dc.identifier.uri http://hdl.handle.net/10251/49948
dc.description.abstract All materials present in the core of a nuclear reactor are activated by neutron irradiation. The activity so generated produces a dose around the material. This dose is a potential risk for workers in the surrounding area when materials are withdrawn from the reactor. Therefore, it is necessary to assess the activity generated and the dose produced. In previous works, neutron activation of control rods and doses around the storage pool where they are placed have been calculated for a Boiling Water Reactor using the MCNP5 code based on the Monte Carlo method. Most of the activation is produced indeed in stainless steel components of the nuclear reactor core not only control rods. In this work, a stainless steel sample is irradiated in the Training Reactor AKR-2 of the Technical University Dresden. Dose measurements around the sample have been performed for different times after the irradiation. Experimental dosimetric values are compared with results of Monte Carlo simulation of the irradiation. Comparison shows a good agreement. Hence, the activation Monte Carlo model can be considered as validated. es_ES
dc.language Inglés es_ES
dc.publisher Elsevier es_ES
dc.relation.ispartof Radiation Physics and Chemistry es_ES
dc.rights Reserva de todos los derechos es_ES
dc.subject Monte Carlo es_ES
dc.subject Neutron activation es_ES
dc.subject Dose estimation es_ES
dc.subject Nuclear reactor es_ES
dc.subject.classification INGENIERIA NUCLEAR es_ES
dc.title Application of dosimetry measurements to analyze the neutron activation of a stainless steel sample in a training nuclear reactor es_ES
dc.type Artículo es_ES
dc.identifier.doi 10.1016/j.radphyschem.2014.05.013
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.; Gallardo Bermell, S.; Weirich, F.; Hansen, W. (2014). Application of dosimetry measurements to analyze the neutron activation of a stainless steel sample in a training nuclear reactor. Radiation Physics and Chemistry. 104:368-371. doi:10.1016/j.radphyschem.2014.05.013 es_ES
dc.description.accrualMethod S es_ES
dc.relation.publisherversion http://dx.doi.org/10.1016/j.radphyschem.2014.05.013 es_ES
dc.description.upvformatpinicio 368 es_ES
dc.description.upvformatpfin 371 es_ES
dc.type.version info:eu-repo/semantics/publishedVersion es_ES
dc.description.volume 104 es_ES
dc.relation.senia 284823


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