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New measurement of the 242Pu(n,γ) cross section at n-TOF-EAR1 for MOX fuels: Preliminary results in the RRR
- Source :
- EPJ Web Conf., ND 2016 International Conference on Nuclear Data for Science and Technology, ND 2016 International Conference on Nuclear Data for Science and Technology, Sep 2016, Bruges, Belgium. pp.11045, ⟨10.1051/epjconf/201714611045⟩, UPCommons. Portal del coneixement obert de la UPC, Universitat Politècnica de Catalunya (UPC), The European physical journal / Web of Conferences, 146, Art.Nr. 11045, Digibug. Repositorio Institucional de la Universidad de Granada, instname, International Conference on Nuclear Data for Science and Technology (ND2016), 11.-16.09.16, Bruges, Belgium, 11.-16.09.16, Bruges, BelgiumEuropean Physical Journal Web of Conferences, idUS. Depósito de Investigación de la Universidad de Sevilla, ResearcherID, Recercat. Dipósit de la Recerca de Catalunya, EPJ Web of Conferences, Vol 146, p 11045 (2017)
- Publication Year :
- 2017
-
Abstract
- 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.<br />This measurement has received funding from the EC FP7 Programme under the projects NEUTANDALUS (Grant No. 334315) and CHANDA (Grant No. 605203), and the Spanish Ministry of Economy and Competitiveness projects FPA2013- 45083-P and FPA2014-53290-C2-2-P.
- Subjects :
- Nuclear reaction
nTOF
QC1-999
Nuclear engineering
Context (language use)
CERN nTOF
Neutron
[PHYS.NEXP]Physics [physics]/Nuclear Experiment [nucl-ex]
01 natural sciences
7. Clean energy
Physics and Astronomy (all)
Nuclear reactors
Reactors nuclears
0103 physical sciences
CERN
Neutron cross section
Nuclear Physics - Experiment
ddc:530
242Pu neutron capture
010306 general physics
MOX fuel
Neutrons
Energies::Energia nuclear [Àrees temàtiques de la UPC]
Fissile material
Cross section
Física [Àrees temàtiques de la UPC]
010308 nuclear & particles physics
Physics
Spent nuclear fuel
Neutron temperature
13. Climate action
neutron time-of-flight measurement
Subjects
Details
- Language :
- English
- ISSN :
- 2100014X
- Database :
- OpenAIRE
- Journal :
- EPJ Web Conf., ND 2016 International Conference on Nuclear Data for Science and Technology, ND 2016 International Conference on Nuclear Data for Science and Technology, Sep 2016, Bruges, Belgium. pp.11045, ⟨10.1051/epjconf/201714611045⟩, UPCommons. Portal del coneixement obert de la UPC, Universitat Politècnica de Catalunya (UPC), The European physical journal / Web of Conferences, 146, Art.Nr. 11045, Digibug. Repositorio Institucional de la Universidad de Granada, instname, International Conference on Nuclear Data for Science and Technology (ND2016), 11.-16.09.16, Bruges, Belgium, 11.-16.09.16, Bruges, BelgiumEuropean Physical Journal Web of Conferences, idUS. Depósito de Investigación de la Universidad de Sevilla, ResearcherID, Recercat. Dipósit de la Recerca de Catalunya, EPJ Web of Conferences, Vol 146, p 11045 (2017)
- Accession number :
- edsair.doi.dedup.....87627e8e4c33430c8001e65ea4bf9b62