Resonance parameters of 240Pu

Kolar, W.; Böckhoff, K. H.

doi:10.1016/0022-3107(68)90003-8

Cited by 22 publications

(4 citation statements)

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“…Among such resonances, two were resolved at 782 and 1402 eV. Apart from Bouland et al [19], Guerrero et al [66] provided resonance parameters, analyzing capture data from n_TOF [67] and transmission data from Kolar and Böckhoff [68]. In these resonances, the radiation widths proposed by Bouland et al and Guerrero were adopted along with the common fission widths they used.…”

Section: Resonances With Large Fission Widthsmentioning

confidence: 99%

Investigation of the Pu240(n,f) reaction at the n_TOF/EAR2 facility in the 9 meV–6 MeV range

Stamatopoulos¹,

Tsinganis²,

Colonna³

et al. 2020

Phys. Rev. C

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Background: Nuclear waste management is considered amongst the major challenges in the field of nuclear energy. A possible means of addressing this issue is waste transmutation in advanced nuclear systems, whose operation requires a fast neutron spectrum. In this regard, the accurate knowledge of neutron-induced reaction cross sections of several (minor) actinide isotopes is essential for design optimization and improvement of safety margins of such systems. One such case is 240 Pu, due to its accumulation in spent nuclear fuel of thermal reactors and its usage in fast reactor fuel. The measurement of the 240 Pu(n, f) cross section was previously attempted at the CERN n_TOF facility EAR1 measuring station using the time-of-flight technique. Due to the low amount of available material and the given flux at EAR1, the measurement had to last several months to achieve a sufficient statistical accuracy. This long duration led to detector deterioration due to the prolonged exposure to the high α activity of the fission foils, therefore the measurement could not be successfully completed. Purpose: It is aimed to determine whether it is feasible to study neutron-induced fission at n_TOF/EAR2 and provide data on the 240 Pu(n, f) reaction in energy regions requested for applications. Methods: The study of the 240 Pu(n, f) reaction was made at a new experimental area (EAR2) with a shorter flight path which delivered on average 30 times higher flux at fast neutron energies. This enabled the measurement to be performed much faster, thus limiting the exposure of the detectors to the intrinsic activity of the fission foils. The experimental setup was based on microbulk Micromegas detectors and the time-of-flight data were analyzed with an optimized pulse-shape analysis algorithm. Special attention was dedicated to the estimation of the non-negligible counting loss corrections with the development of a new methodology, and other corrections were estimated via Monte Carlo simulations of the experimental setup. Results: This new measurement of the 240 Pu(n, f) cross section yielded data from 9 meV up to 6 MeV incident neutron energy and fission resonance kernels were extracted up to 10 keV. Conclusions: Neutron-induced fission of high activity samples can be successfully studied at the n_TOF/EAR2 facility at CERN covering a wide range of neutron energies, from thermal to a few MeV.

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Section: Resonances With Large Fission Widthsmentioning

confidence: 99%

Investigation of the Pu240(n,f) reaction at the n_TOF/EAR2 facility in the 9 meV–6 MeV range

Stamatopoulos¹,

Tsinganis²,

Colonna³

et al. 2020

Phys. Rev. C

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“…The data have allowed performing the resonance analysis up to 2 keV. The cross section was obtained from the combined analysis with the transmission data by Kolar et al [15]. The TAC has been used as well for measuring the first TOF data set in the entire resolved resonance region for the 243 Am(n,γ) reaction.…”

Section: Measurements At N Tofmentioning

confidence: 99%

Neutron Capture Measuremetns on Minor Actinides at the n_TOF Facility at CERN: Past, Present and Future

Cano‐Ott¹,

Álvarez‐Velarde²,

González‐Romero³

et al. 2011

J. Korean Phy. Soc.

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The successful development of advanced nuclear systems for sustainable energy production and nuclear waste management depends on high quality nuclear data libraries. Recent sensitivity studies and reports [1-3] have identified the need for substantially improving the accuracy of neutron cross-section data for minor actinides. The n TOF collaboration has initiated an ambitious experimental program for the measurement of neutron capture cross sections of minor actinides. Two experimental setups have been constructed for this purpose: a Total Absorption Calorimeter (TAC) [4] for measuring neutron capture cross-sections of low-mass and/or radioactive samples and a set of two low neutron sensitivity C6D6 detectors for the less radioactive materials.

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“…The n TOF capture data are analyzed together with the transmission data of Kolar and Böckoff [17] (GELINA, 1968), also included in the work of Bouland et al [10] and the evaluated data files. The 240 Pu level spacing is D ∼ 12 eV and the resonances are well resolved up to several keV.…”

Section: Pu Cross Sectionmentioning

confidence: 99%

The neutron capture cross sections of ²³⁷Np(n,γ) and ²⁴⁰Pu(n,γ) and its relevance in the transmutation of nuclear waste

Guerrero

Abbondanno

Aerts

et al. 2007

Nd2007

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Abstract. Neutron capture cross sections of actinides are of great relevance for the Transmutation of Nuclear Waste in Accelerator Driven Systems (ADS) and Generation-IV reactors. The neutron capture cross sections of 237 Np and 240 Pu were measured at the n TOF facility with a Total Absorption Calorimeter. The data have been analyzed with the SAMMY code. The corresponding covariance matrices have been generated. The final cross sections are presented and compared to the previously existing ones.

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Resonance parameters of 240Pu

Cited by 22 publications

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Investigation of the Pu240(n,f) reaction at the n_TOF/EAR2 facility in the 9 meV–6 MeV range

Investigation of the Pu240(n,f) reaction at the n_TOF/EAR2 facility in the 9 meV–6 MeV range

Neutron Capture Measuremetns on Minor Actinides at the n_TOF Facility at CERN: Past, Present and Future

The neutron capture cross sections of ²³⁷Np(n,γ) and ²⁴⁰Pu(n,γ) and its relevance in the transmutation of nuclear waste

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Resonance parameters of 240Pu

Cited by 22 publications

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Investigation of the Pu240(n,f) reaction at the n_TOF/EAR2 facility in the 9 meV–6 MeV range

Investigation of the Pu240(n,f) reaction at the n_TOF/EAR2 facility in the 9 meV–6 MeV range

Neutron Capture Measuremetns on Minor Actinides at the n_TOF Facility at CERN: Past, Present and Future

The neutron capture cross sections of 237Np(n,γ) and 240Pu(n,γ) and its relevance in the transmutation of nuclear waste

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The neutron capture cross sections of ²³⁷Np(n,γ) and ²⁴⁰Pu(n,γ) and its relevance in the transmutation of nuclear waste