Search results for "242Pu"

showing 3 items of 3 documents

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

2016

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…

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
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Radiative neutron capture on 242Pu in the resonance region at the CERN n_TOF-EAR1 facility

2018

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 to the long-term sustainability of nuclear energy. However, an extensive use of MOX fuels, in particular in fast reactors, requires more accurate capture and fission cross sections for some Pu isotopes. In the case of 242Pu there are sizable discrepancies among the existing capture cross-section measurements included in the evaluations (all from the 1970s) resulting in an uncertainty as high as 35% in the fast energy region. Moreover, postirradiation experiments evaluat…

PRIRODNE ZNANOSTI. Fizika.neutron capture 242Pu resonance analysis n_TOFresonance analysisn_TOF242PuNATURAL SCIENCES. Physics.neutron capture
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Measurement of the Pu-242(n,gamma) cross section from thermal to 500 keV at the Budapest research reactor and CERN n_TOF-EAR1 facilities

2019

The design and operation of innovative nuclear systems requires a better knowledge of the capture and fission cross sections of the Pu isotopes. For the case of capture on 242Pu, a reduction of the uncertainty in the fast region down to 8-12% is required. Moreover, aiming at improving the evaluation of the fast energy range in terms of average parameters, the OECD NEA High Priority Request List (HPRL) requests high-resolution capture measurements with improved accuracy below 2 keV. The current uncertainties also affect the thermal point, where previous experiments deviate from each other by 20%. A fruitful collaboration betwen JGU Mainz and HZ Dresden-Rossendorf within the EC CHANDA project…

PhysicsLarge Hadron ColliderIsotope010308 nuclear & particles physicsFissionPhysicsQC1-999n_TOF 242Pu neutron capture neutron time of flight[PHYS.NEXP]Physics [physics]/Nuclear Experiment [nucl-ex]01 natural sciences7. Clean energyResonance (particle physics)Nuclear physicsStack (abstract data type)0103 physical sciencesNeutronResearch reactorNuclear Physics - ExperimentNeutron activation analysis010306 general physics
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