Now showing items 1-5 of 5

    • Cross section measurements of 155,157Gd(n, γ) induced by thermal and epithermal neutrons 

      n-TOF Collaboration (2019-01-28)
      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 ...
    • First results of the140ce(N,ү)141ce cross-section measurement at n_tof 

      n-TOF Collaboration; Amaducci, Simone; Colonna, Nicola; Cosentino, Luigi; Cristallo, Sergio; Finocchiaro, Paolo; Krticka, Milan; Massimi, Cristian; Mastromarco, Mario; Mazzone, Annamaria; Mengoni, Alberto; Valenta, Stanislav; Aberle, Oliver; Alcayne, Victor; Andrzejewski, Józef; Audouin, Laurent; Babiano-Suarez, Victor; Bacak, Michael; Barbagallo, Massimo; Bennett, Samuel; Berthoumieux, Eric; Billowes, Jon; Bosnar, Damir; Brown, Adam; Busso, Maurizio; Caamaño, Manuel; Caballero-Ontanaya, Luis; Calviño, Francisco; Calviani, Marco; Cano-Ott, Daniel; Casanovas, Adria; Cerutti, Francesco; Chiaveri, Enrico; Cortés, Guillem; Cortés-Giraldo, Miguel; Damone, Lucia Anna; Davies, Paul John; Diakaki, Maria; Dietz, Mirco; Domingo-Pardo, Cesar; Dressler, Rugard; Ducasse, Quentin; Dupont, Emmeric; Durán, Ignacio; Eleme, Zinovia; Fernández-Domínguez, Beatriz; Ferrari, Alfredo; Furman, Valter; Göbel, Kathrin; Garg, Ruchi; Rauscher, Thomas (2021-06-17)
      An accurate measurement of the140Ce(n,ү) energy-dependent cross-section was performed at the n_TOF facility at CERN. This cross-section is of great importance because it represents a bottleneck for the s-process nucleosynthesis ...
    • Measurement and resonance analysis of the S 33 (n,α) Si 30 cross section at the CERN n-TOF facility in the energy region from 10 to 300 keV 

      n-TOF Collaboration (2018-06)
      The S33(n,α)Si30 cross section has been measured at the neutron time-of-flight (n-TOF) facility at CERN in the neutron energy range from 10 to 300 keV relative to the B10(n,α)Li7 cross-section standard. Both reactions were ...
    • Measurements of high-energy neutron-induced fission of (nat)Pb and (209)Bi 

      Tarrio, D.; Tassan-Got, L.; Audouin, L.; Berthier, B.; Duran, I.; Ferrant, L.; Isaev, S.; Le Naour, C.; Paradela, C.; Stephan, C.; Trubert, D.; Abbondanno, U.; Aerts, G.; Alvarez, H.; Alvarez-Velarde, F.; Andriamonje, S.; Andrzejewski, J.; Assimakopoulos, P.; Badurek, G.; Baumann, P.; Becvar, F.; Berthoumieux, E.; Calvino, F.; Calviani, M.; Cano-Ott, D.; Capote, R.; Carrapico, C.; Cennini, P.; Chepel, V.; Chiaveri, E.; Colonna, N.; Cortes, G.; Couture, A.; Cox, J.; Dahlfors, M.; David, S.; Dillmann, I.; Domingo-Pardo, C.; Dridi, W.; Eleftheriadis, C.; Embid-Segura, M.; Ferrari, A.; Ferreira-Marques, R.; Fujii, K.; Furman, W.; Goncalves, I.; Gonzalez-Romero, E.; Gramegna, F.; Guerrero, C.; Rauscher, T.; n-TOF Collaboration (EDP Sciences, 2010)
      The CERN Neutron Time-Of-Flight (n_TOF) facility is well suited to measure low cross sections as those of neutron-induced fission in subactinides. The cross section ratios of (nat)Pb and (209)Bi relative to (235)U and ...
    • Radiative neutron capture on Pu 242 in the resonance region at the CERN n-TOF-EAR1 facility 

      Lerendegui-Marco, J.; Guerrero, C.; Mendoza, E.; Quesada, J. M.; Eberhardt, K.; Junghans, A. R.; Krtička, M.; Aberle, O.; Andrzejewski, J.; Audouin, L.; Bécares, V.; Bacak, M.; Balibrea, J.; Barbagallo, M.; Barros, S.; Bečvář, F.; Beinrucker, C.; Berthoumieux, E.; Billowes, J.; Bosnar, D.; Brugger, M.; Caamaño, M.; Calviño, F.; Calviani, M.; Cano-Ott, D.; Cardella, R.; Casanovas, A.; Castelluccio, D. M.; Cerutti, F.; Chen, Y. H.; Chiaveri, E.; Colonna, N.; Cortés, G.; Cortés-Giraldo, M. A.; Cosentino, L.; Damone, L. A.; Diakaki, M.; Dietz, M.; Domingo-Pardo, C.; Dressler, R.; Dupont, E.; Durán, I.; Fernández-Domínguez, B.; Ferrari, A.; Ferreira, P.; Finocchiaro, P.; Furman, V.; Göbel, K.; García, A. R.; Rauscher, T.; n-TOF Collaboration (2018-02-06)
      The spent fuel of current nuclear reactors contains fissile plutonium isotopes that can be combined with uranium to make mixed oxide (MOX) fuel. In this way the Pu from spent fuel is used in a new reactor cycle, contributing ...