Quasi-differential elastic and inelastic neutron scattering from iron in the MeV energy range

Daskalakis, A.; Blain, E.; McDermott, B.; Bahran, Rian; Danon, Y.; Barry, D. P.; Block, Robert C.; Rapp, M. J.; Epping, Brian; Leinweber, G.

doi:10.1016/j.anucene.2017.07.007

Cited by 9 publications

(9 citation statements)

References 13 publications

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“…"White source" laboratories produce neutrons by spallation (e.g., LANSCE [6][7][8][9][10][11][12]42]) or photo-production (RPI [20,[91][92][93], GELINA [15][16][17][18][19], nELBE [21][22][23][24][25], ORELA [13,14], Helios [94,95]). The neutron fluence is well collimated and very nearly planar at the sample which is illuminated rather uniformly.…”

Section: White Neutron Sourcesmentioning

confidence: 99%

Templates of expected measurement uncertainties for (n, xn) cross sections

Vanhoy,

Haight,

Hicks

et al. 2023

EPJ Nuclear Sci. Technol.

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A template is provided for evaluating experimental uncertainties for neutron elastic and inelastic scattering cross sections andγ-ray production cross sections from (n, xn) measurements at laboratories with monoenergetic or white neutron sources. A typical range of uncertainties is presented for experiments detecting the scattered neutrons or the resulting de-excitationγrays based on a survey of available data and input from many experimentalists and theorists with extensive knowledge in the field. Models commonly used to evaluate the resulting cross-sections are also discussed. Suggestions are made regarding what experimental and uncertainty information is needed for data evaluations and should be included when reporting experimental (n, xn) cross sections. Uncertainty values and correlations are recommended if these values cannot be estimated for past data from the literature.

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Section: White Neutron Sourcesmentioning

confidence: 99%

Templates of expected measurement uncertainties for (n, xn) cross sections

Vanhoy,

Haight,

Hicks

et al. 2023

EPJ Nuclear Sci. Technol.

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show abstract

“…An assessment of the systematic uncertainty in this methodology was derived from a sample of carbon that was measured with the sample of interest in all experiments. Previous measurements were reported for Mo [1], Zr [3], U-238 [4], Fe [5], Mo and Be [6] and Pb [7]. For the case of Fe it was also possible to obtain the ratio of inelastic to elastic scattering for the first inelastic state, and the elastic only scattering yield [5].…”

Section: Introductionmentioning

confidence: 98%

“…Previous measurements were reported for Mo [1], Zr [3], U-238 [4], Fe [5], Mo and Be [6] and Pb [7]. For the case of Fe it was also possible to obtain the ratio of inelastic to elastic scattering for the first inelastic state, and the elastic only scattering yield [5]. Scattering data from these measurements was used in evaluation of U-238 for the CIELO project [8] and validation of the ENDF/B-8.0 evaluations of Be [9].…”

Section: Introductionmentioning

confidence: 99%

Experiments with neutron induced neutron emission from U-235, Pu-239, and graphite

et al. 2020

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A neutron induced neutron emission experiment was conducted as the Los Alamos Neutron Science Center (LANSCE) facility at Los Alamos National Laboratory (LANL). In this experiment, a sample was placed in a well collimated neutron beam and was surrounded by an array of 28 fast neutron detectors (EJ-309). The experiment was performed with a neutron flight path of 21.5 m from the source to the sample, and 1 m from the sample to the detectors. The neutron emission from the sample was measured as a function of neutron time of flight covering an incident energy range from 0.7- 20 MeV. The samples included U-235, Pu-239, carbon (graphite), and blanks that matched the encapsulation of the sample. The measured samples were constantly cycled in and out of the neutron beam. This type of experiment measures neutron emission from all reactions occurring in the sample such as fission and elastic and inelastic scattering. Similar to the methodology previously developed at RPI [1], the measurements were compared with detailed simulations of the experiment using different cross section evaluations for the sample. The observed differences can be attributed to the evaluated neutron cross section and angular distributions. The carbon sample was used as a reference to validate both the experiment and simulation methodology and showed good agreement between experiments and simulations. A review of the experimental setup, analysis methods, and some of the results will be presented.

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“…Observed di↵erences between measured data and Monte Carlo calculations have been used by evaluators to constrain their models [1]. Past measurements using the HES system included graphite (carbon) [2], beryllium [3], molybdenum [3], zirconium [4], 238 U [5], iron [6], lead [7], and copper [8].…”

Section: Introductionmentioning

confidence: 99%

“…This study revisits previously measured 238 U data to describe a novel approach that separates the fission contribution from other reaction channels. This method relies on in-beam response functions and builds on previously described techniques used to quantify the elastic-only contribution [6,9]. Results are compared with MCNP [10] simulations to demonstrate proof-of-principle.…”

Section: Introductionmentioning

confidence: 99%

Method to Compare Fission-to-Scattering Ratios using Uranium-238

et al. 2023

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A novel method was developed to separate the 238U fission contribution measured in quasi-differential time-of-flight scattering experiments in order to isolate the elastic and inelastic events. Pulse height distributions from in-beam measurements were used to generate response functions, which were used to reconstruct the 238U prompt fission neutron spectra. This method was validated by reconstructing the measured 252Cf spontaneous fission pulse height distribution. Monte Carlo calculations were used to model the experiment. Good agreement was observed between the measured and calculated 238U fission contribution.

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Quasi-differential elastic and inelastic neutron scattering from iron in the MeV energy range

Cited by 9 publications

References 13 publications

Templates of expected measurement uncertainties for (n, xn) cross sections

Templates of expected measurement uncertainties for (n, xn) cross sections

Experiments with neutron induced neutron emission from U-235, Pu-239, and graphite

Method to Compare Fission-to-Scattering Ratios using Uranium-238

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