New measurement of the 242Pu(n,γ) cross section at n_TOF

被引：4

作者：

Lerendegui-Marco, J. ^{[1
]}

Guerrero, C. ^{[1
]}

Cortes-Giraldo, M. A. ^{[1
]}

Quesada, J. M. ^{[1
]}

Mendoza, E. ^{[2
]}

Cano-Ott, D. ^{[2
]}

Eberhardt, K. ^{[3
]}

Junghans, A. ^{[4
]}

机构：

[1] Univ Seville, Dept Fis Atom Mol & Nucl, E-41012 Seville, Spain

[2] Ctr Invest Energet Medioambientales & Tecnol CIEM, Madrid 28040, Spain

[3] Johannes Gutenberg Univ Mainz, D-55128 Mainz, Germany

[4] Helmholtz Zentrum Dresden Rossendorf, D-01314 Dresden, Germany

[5] European Ctr Nucl Res CERN, CH-1211 Geneva, Switzerland

来源：

WONDER-2015 - 4TH INTERNATIONAL WORKSHOP ON NUCLEAR DATA EVALUATION FOR REACTOR APPLICATIONS | 2016年 / 111卷

关键词：

ENERGY-RANGE; NEUTRON-FLUX; FACILITY; RATIOS; PU-242; AU-197;

D O I：

10.1051/epjconf/201611102005

中图分类号：

TL [原子能技术]; O571 [原子核物理学];

学科分类号：

0827 ; 082701 ;

摘要：

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 rich in Pu, a better knowledge of the capture and fission cross sections of the Pu isotopes becomes very important. In particular, a new series of cross section evaluations have been recently carried out jointly by the European (JEFF) and United States (ENDF) nuclear data agencies. For the case of Pu-242, the two only neutron capture time-of-flight measurements available, from 1973 and 1976, are not consistent with each other, which calls for a new time-of flight capture cross section measurement. In order to contribute to a new evaluation, we have perfomed a neutron capture cross section measurement at the n_TOF-EAR1 facility at CERN using four C6D6 detectors, using a high purity target of 95 mg. The preliminary results assessing the quality and limitations (background, statistics and gamma-flash effects) of this new experimental data are presented and discussed, taking into account that the aimed accuracy of the measurement ranges between 7% and 12% depending on the neutron energy region.

引用

页数：7

共 50 条

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[2] Measurement of the 242Pu(n,f) Cross Section at the CERN n_TOF Facility
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[3] New measurement of the 242Pu(n,γ) cross section at n_TOF-EAR1 for MOX fuels: Preliminary results in the RRR
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[6] Measurement of the 242Pu(n,γ) cross section from thermal to 500 keV at the Budapest research reactor and CERN n_TOF-EAR1 facilities
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Dressler, R.
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Duran, I
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[7] Measurement of the 197Au(n,γ) cross section at n_TOF: towards a new standard
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[9] 242Pu absolute neutron-capture cross section measurement
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