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Artículo
Cross section measurements of 155,157Gd(n, γ) induced by thermal and epithermal neutrons
(Springer Nature, 2019)
Neutron capture cross section measurements on 155Gd and 157Gd were performed using the time-of-flight technique at the n_TOF facility at CERN on isotopically enriched samples. The measurements were carried out in the n_TOF ...
Artículo
New measurement of the 242Pu(n,γ) cross section at n_TOF
(EDP Sciences, 2016)
The use of MOX fuel (mixed-oxide fuel made of UO2 and PuO2) in nuclear reactors allows substituting a large fraction of the enriched Uranium by Plutonium reprocessed from spent fuel. With the use of such new fuel composition ...
Artículo
First Measurement of Several β-Delayed Neutron Emitting Isotopes Beyond N=126
(American Physical Society, 2016)
The β-delayed neutron emission probabilities of neutron rich Hg and Tl nuclei have been measured together with β-decay half-lives for 20 isotopes of Au, Hg, Tl, Pb, and Bi in the mass region N≳126. These are the heaviest ...
Artículo
Measurement and analysis of the 243 Am neutron capture cross section at the n_TOF facility at CERN
(American Physical Society, 2014)
Background: The design of new nuclear reactors and transmutation devices requires to reduce the present neutron cross section uncertainties of minor actinides. Purpose: Improvement of the Am243(n,γ) cross section uncertainty. ...
Artículo
Production yields at the distal fall-off of the β+ emitters 11C and 13N for in-vivo range verification in proton therapy
(Elsevier, 2022)
In proton therapy, Positron Emission Tomography (PET) range verification relies on the comparison of the measured and estimated activity distributions from β+ emitters produced by the proton beam in the patient. The accuracy ...
Artículo
New measurement of the242Pu(n,γ) cross section at n-TOF-EAR1 for MOX fuels: Preliminary results in the RRR
(EDP Sciences, 2017)
The spent fuel of current nuclear reactors contains fissile plutonium isotopes that can be combined with 238U to make mixed oxide (MOX) fuel. In this way the Pu from spent fuel is used in a new reactor cycle, contributing ...