Dosimetry of the mixed field irradiation facility CALIBAN
| Autor: | Christelle Huet, I. Robbes, R. Médioni, François Trompier, B. Asselineau |
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| Přispěvatelé: | Institut de Radioprotection et de Sûreté Nucléaire (IRSN) |
| Jazyk: | angličtina |
| Rok vydání: | 2008 |
| Předmět: |
Experimental reactors
Physics::Instrumentation and Detectors irradiation facilities [SDV]Life Sciences [q-bio] Physics::Medical Physics Monte Carlo method Analytical chemistry Radiation 01 natural sciences 030218 nuclear medicine & medical imaging Dosimeters 03 medical and health sciences Kerma 0302 clinical medicine Dosimetry 0103 physical sciences Neutron Irradiation Instrumentation 010308 nuclear & particles physics Chemistry Radiochemistry Neutron temperature Thermoluminescent dosimeter neutron components Aluminum |
| Zdroj: | Radiation Measurements Radiation Measurements, 2008, 43 (2-6), pp.1077-1080. ⟨10.1016/j.radmeas.2007.11.031⟩ |
| Popis: | The dosimetry of the experimental reactor CALIBAN was established for photon and neutron components, and the kerma variations were evaluated according to position (distance from the core, height, angle with the median room axis). Dosimetry was performed with TLD (Al2O3) for the photon component, and with passive silicon diodes, activation detectors (Au, In, Ni, Mg, Cu) and alanine pellets measured by EPR spectrometry for the neutron component. The neutron energy distribution was experimentally evaluated at various distances based on the activities measured at the activated foil using the SNAC2 software. It was then compared with those calculated with the Monte Carlo code MCNPX. © 2007 Elsevier Ltd. All rights reserved. |
| Databáze: | OpenAIRE |
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