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| Campo DC | Valor | Lengua/Idioma |
|---|---|---|
| dc.provenance | CONICET | - |
| dc.creator | Triviño, Juan Sebastián | - |
| dc.creator | Vedelago, José Alberto | - |
| dc.creator | Cantargi, Florencia Olga | - |
| dc.creator | Keil, Walter Miguel | - |
| dc.creator | Figueroa, R. | - |
| dc.creator | Mattea, Facundo | - |
| dc.creator | Chautemps, Norma Adriana | - |
| dc.creator | Santibañez, M. | - |
| dc.creator | Valente, Mauro Andres | - |
| dc.date | 2018-09-07T19:44:23Z | - |
| dc.date | 2018-09-07T19:44:23Z | - |
| dc.date | 2016-10-17 | - |
| dc.date | 2018-08-15T13:57:59Z | - |
| dc.date.accessioned | 2019-04-29T15:33:52Z | - |
| dc.date.available | 2019-04-29T15:33:52Z | - |
| dc.date.issued | 2016-10-17 | - |
| dc.identifier | Triviño, Juan Sebastián; Vedelago, José Alberto; Cantargi, Florencia Olga; Keil, Walter Miguel; Figueroa, R.; et al.; Neutron dose estimation in a zero power nuclear reactor; Pergamon-Elsevier Science Ltd; Radiation Physics and Chemistry (Oxford); 127; 17-10-2016; 62-67 | - |
| dc.identifier | 0969-806X | - |
| dc.identifier | http://hdl.handle.net/11336/58826 | - |
| dc.identifier | CONICET Digital | - |
| dc.identifier | CONICET | - |
| dc.identifier.uri | http://rodna.bn.gov.ar:8080/jspui/handle/bnmm/296638 | - |
| dc.description | This work presents the characterization and contribution of neutron and gamma components to the absorbed dose in a zero power nuclear reactor. A dosimetric method based on Fricke gel was implemented to evaluate the separation between dose components in the mixed field. The validation of this proposed method was performed by means of direct measurements of neutron flux in different positions using Au and Mg-Ni activation foils. Monte Carlo simulations were conversely performed using the MCNP main code with a dedicated subroutine to incorporate the exact complete geometry of the nuclear reactor facility. Once nuclear fuel elements were defined, the simulations computed the different contributions to the absorbed dose in specific positions inside the core. Thermal/epithermal contributions of absorbed dose were assessed by means of Fricke gel dosimetry using different isotopic compositions aimed at modifying the sensitivity of the dosimeter for specific dose components. Clear distinctions between gamma and neutron capture dose were obtained. Both Monte Carlo simulations and experimental results provided reliable estimations about neutron flux rate as well as dose rate during the reactor operation. Simulations and experimental results are in good agreement in every positions measured and simulated in the core. | - |
| dc.description | Fil: Triviño, Juan Sebastián. Universidad Nacional de Córdoba; Argentina. Comisión Nacional de Energía Atómica; Argentina | - |
| dc.description | Fil: Vedelago, José Alberto. Consejo Nacional de Investigaciones Científicas y Técnicas. Centro Científico Tecnológico Conicet - Córdoba. Instituto de Física Enrique Gaviola. Universidad Nacional de Córdoba. Instituto de Física Enrique Gaviola; Argentina | - |
| dc.description | Fil: Cantargi, Florencia Olga. Comisión Nacional de Energía Atómica. Centro Atómico Bariloche; Argentina | - |
| dc.description | Fil: Keil, Walter Miguel. Universidad Nacional de Córdoba; Argentina. Comisión Nacional de Energía Atómica; Argentina | - |
| dc.description | Fil: Figueroa, R.. Universidad de La Frontera; Chile | - |
| dc.description | Fil: Mattea, Facundo. Universidad Nacional de Córdoba; Argentina. Universidad Nacional de Córdoba. Facultad de Ciencias Químicas; Argentina. Consejo Nacional de Investigaciones Científicas y Técnicas; Argentina | - |
| dc.description | Fil: Chautemps, Norma Adriana. Comisión Nacional de Energía Atómica; Argentina | - |
| dc.description | Fil: Santibañez, M.. Universidad de La Frontera; Chile | - |
| dc.description | Fil: Valente, Mauro Andres. Universidad de La Frontera; Chile. Universidad Nacional de Córdoba; Argentina. Consejo Nacional de Investigaciones Científicas y Técnicas. Centro Científico Tecnológico Conicet - Córdoba. Instituto de Física Enrique Gaviola. Universidad Nacional de Córdoba. Instituto de Física Enrique Gaviola; Argentina | - |
| dc.format | application/pdf | - |
| dc.format | application/pdf | - |
| dc.format | application/pdf | - |
| dc.format | application/pdf | - |
| dc.format | application/pdf | - |
| dc.format | application/pdf | - |
| dc.language | eng | - |
| dc.publisher | Pergamon-Elsevier Science Ltd | - |
| dc.relation | info:eu-repo/semantics/altIdentifier/url/http://www.sciencedirect.com/science/article/pii/S0969806X16301906 | - |
| dc.relation | info:eu-repo/semantics/altIdentifier/doi/https://doi.org/10.1016/j.radphyschem.2016.06.011 | - |
| dc.rights | info:eu-repo/semantics/restrictedAccess | - |
| dc.rights | https://creativecommons.org/licenses/by-nc-sa/2.5/ar/ | - |
| dc.source | reponame:CONICET Digital (CONICET) | - |
| dc.source | instname:Consejo Nacional de Investigaciones Científicas y Técnicas | - |
| dc.source | instacron:CONICET | - |
| dc.source.uri | http://hdl.handle.net/11336/58826 | - |
| dc.subject | FRICKE GEL DOSIMETRY | - |
| dc.subject | MCNP | - |
| dc.subject | MONTE CARLO SIMULATIONS | - |
| dc.subject | THERMAL/EPITHERMAL NEUTRON FLUX | - |
| dc.subject | Astronomía | - |
| dc.subject | Ciencias Físicas | - |
| dc.subject | CIENCIAS NATURALES Y EXACTAS | - |
| dc.title | Neutron dose estimation in a zero power nuclear reactor | - |
| dc.type | info:eu-repo/semantics/article | - |
| dc.type | info:eu-repo/semantics/publishedVersion | - |
| dc.type | info:ar-repo/semantics/articulo | - |
| Aparece en las colecciones: | CONICET | |
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