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

Abstract

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.

EXFOR-based simultaneous evaluation of neutron-induced uranium and plutonium fission cross sections for JENDL-5

“…The prior cross section is taken from JENDL-4.0 (below 20 MeV) and JENDL-4.0/HE (above 20 MeV). 240 Pu/ 235 U fission prior and posterior cross section ratios with the experimental cross section ratios used for evaluation [125,128,138,[140][141][142][143][144][145][146][147][148]. The prior cross section is taken from JENDL-4.0 (below 20 MeV) and JENDL-4.0/HE (above 20 MeV).…”

“…• Correlated and uncorrelated partial uncertainties in EXFOR When the correlated and uncorrelated partial uncertainties are in the EXFOR entry separately, we used them for estimation of the correlation coefficients. The quadrature sum of the correlated and uncorrelated partial uncertainties exceeds the total uncertainty in EXFOR 23458.006 [140]. For this dataset, we discarded the uncorrelated partial uncertainty in the EXFOR entry, treated the total uncertainty in the EXFOR entry as uncorrelated, and combined it with the correlated partial uncertainty in the EXFOR entry.…”

Measurement of the $$^{244}$$ 244 Cm and $$^{246}$$ 246 Cm Neutron-Induced Cross Sections at the n_TOF Facility

“…These features have made possible new measurements with shorter half-lives isotopes (i.e. highly radioactive), smaller capture cross-sections and/or smaller samples [12][13][14][15].…”