6533b7d3fe1ef96bd1260b13

RESEARCH PRODUCT

New measurement of the 242Pu(n,γ) cross section at n-TOF-EAR1 for MOX fuels: Preliminary results in the RRR

Simone GilardoniP. C. RoutIgnacio PorrasRene ReifarthJ. BillowesC. LedererE. Leal-cidonchaJ. M. QuesadaL. Tassan-gotA. GawlikThomas RauscherThomas RauscherR. CardellaP. VazP. SchillebeeckxM. DiakakiA. CasanovasAlberto VenturaA. MengoniM. KokkorisHideo HaradaJ. MarganiecJ. MarganiecG. VanniniG. VanniniM. CaamañoA. OpreaJ. HeyseN. PatronisL. CosentinoM. Sabaté-gilarteM. Sabaté-gilarteS. WarrenE. A. MaugeriA. PavlikM. A. Cortés-giraldoC. Domingo-pardoF. CeruttiAriel Tarifeño-saldiviaS. J. LonsdaleE. MendozaE. JerichaR. NolteS. ValentaP. F. MastinuT. GlodariuJ. Lerendegui-marcoV. VarialeArnd R. JunghansA. R. GarcíaPaolo FinocchiaroMarco CalvianiA. KimuraJ. A. RyanA. SaxenaA. G. SmithP. M. MilazzoI. F. GonçalvesM. MastromarcoPhilip WoodsF. CalviñoH. LeebA. S. BrownAnton WallnerR. VlastouJ. PerkowskiM. B. Gómez-hornillosI. DuranJavier PraenaS. Lo MeoS. Lo MeoF. GunsingP. FerreiraY. H. ChenMario BarbagalloD. SchumannF. MingroneJ. AndrzejewskiJ. BalibreaE. ChiaveriE. ChiaveriE. ChiaveriA. MasiG. TaglienteS. HeinitzDamir BosnarD. Cano-ottCarlo RubbiaG. CortesCristian MassimiCristian MassimiA. StamatopoulosY. KadiD. G. JenkinsK. GöbelR. DresslerV. VlachoudisD. MacinaP. KavriginAlfredo FerrariE. GonzálezT. WrightE. GriesmayerL. A. DamoneL. A. DamoneM. KrtičkaO. AberleT. MartinezN. V. SosninAnnamaria MazzonePetar ŽUgecPetar ŽUgecB. Fernández-domínguezJ. L. TainAlexandru NegretF. KäppelerN. KivelKlaus EberhardtD. RadeckE. BerthoumieuxL. AudouinA. KalamaraA. MusumarraDeniz KurtulgilNicola ColonnaCarlos GuerreroE. DupontF. BečvářM. BacakM. Bacak

subject

Nuclear reactionnTOFQC1-999Nuclear engineeringContext (language use)CERN nTOFNeutron[PHYS.NEXP]Physics [physics]/Nuclear Experiment [nucl-ex]01 natural sciences7. Clean energyPhysics and Astronomy (all)Nuclear reactorsReactors nuclears0103 physical sciencesCERNNeutron cross sectionNuclear Physics - ExperimentNeutronddc:530242Pu neutron capture010306 general physicsMOX fuelNeutrons:Energies::Energia nuclear [Àrees temàtiques de la UPC]Fissile materialCross section:Física [Àrees temàtiques de la UPC]010308 nuclear & particles physicsPhysicsNuclear reactionSpent nuclear fuelNeutron temperature13. Climate actionneutron time-of-flight measurement

description

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 to the long-term sustainability of nuclear energy. The use of MOX fuels in thermal and fast reactors requires accurate capture and fission cross sections. For the particular case of 242Pu, the previous neutron capture cross section measurements were made in the 70’s, providing an uncertainty of about 35% in the keV region. In this context, the Nuclear Energy Agency recommends in its “High Priority Request List” and its report WPEC-26 that the capture cross section of 242Pu should be measured with an accuracy of at least 7–12% in the neutron energy range between 500 eV and 500 keV. This work presents a brief description of the measurement performed at n TOF-EAR1, the data reduction process and the first ToF capture measurement on this isotope in the last 40 years, providing preliminary individual resonance parameters beyond the current energy limits in the evaluations, as well as a preliminary set of average resonance parameters.

10.1051/epjconf/201714611045http://hdl.handle.net/20.500.11769/357692