D. P. Barry

United States Naval Research Laboratory

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Y. Danon

Rensselaer Polytechnic Institute

R.C. Block

Rensselaer Polytechnic Institute

M. J. Rapp

United States Naval Research Laboratory

G. Leinweber

United States Naval Research Laboratory

N. J. Drindak

Bechtel (United States)

A. Daskalakis

United States Naval Research Laboratory

Rian Bahran

Los Alamos National Laboratory

Amanda M. Lewis

University of Basel

B. Epping

United States Naval Research Laboratory

B. McDermott

Nuclear Energy Agency

Cooperative Institutions

Rensselaer Polytechnic Institute

Los Alamos National Laboratory

Oak Ridge National Laboratory

Bechtel (United States)

United States Naval Research Laboratory

Lockheed Martin (United States)

International Atomic Energy Agency

Brookhaven National Laboratory

Lawrence Livermore National Laboratory

National Technical Information Service

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Measurements of Neutron Scattering from a Copper Sample Using a Quasi-Differential Method in the Region from 2 keV to 20 MeV

Nuclear Science and Engineering (2021)

E. Blain Y. Danon D. P. Barry B. Epping A. Youmans

Neutron scattering from a copper sample was measured at Rensselaer Polytechnic Institute utilizing the quasi-differential method. The measurement spanned the energy range from 0.5 to 20 MeV using the high-energy scattering system and from 2 keV to 0.5 MeV using the new mid-energy scattering system. Copper was selected as a material of interest to measure due to large discrepancies between experiments and simulations of the Zeus benchmark. The Zeus benchmark consists of a copper reflected highly enriched uranium system, and the angular distribution of copper scattering was thought to potentially be the cause of the discrepancy. The copper measurements found differences in the scattering response particularly in the incident energy region from 1 to 2 MeV for the high-energy measurement and from 2 to 4 keV in the mid-energy system. These differences are particularly noticeable at angles near 90 deg in the high-energy system and back angles in the mid-energy system. Additionally, for ENDF/B-VIII.0 there is a large discrepancy at the forward angle in the energy range around 0.5 MeV. For these reasons, a new evaluation of copper scattering utilizing these results is recommended and perhaps could help to improve the agreement with the Zeus benchmarks.

ZEUS (particle detector)

10.1080/00295639.2021.1961542

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Citations (2)

Revised <sup>207</sup>Pb Thermal Capture Gamma-ray Spectrum Evaluation

Amanda M. Lewis D. P. Barry

This report details the revision of the JENDL-4.0 thermal capture gamma-ray spectrum evaluation for 207Pb and the comparison of the current evaluations and the revised spectrum. The history of the available reaction evaluations is described and the defciencies are identifed. The modifed spectrum has an average energy of 7.329 MeV and an average multiplicity of 1.005, leading to a total energy released value of 7.366 MeV, just 0.03% off from the Q-value of the reaction, 7.368 MeV. Based on comparison to the measurements and structure libraries considered, the revised evaluation is closer to reality and should provide more accurate coupled neutron-gamma ray calculations.

Energy spectrum

Multiplicity (mathematics)

10.2172/1903733

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Unresolved resonance region cross section measurements and validation

Y. Danon D. P. Barry Judith C. Brown Abhinav Golas

10.2172/2427312

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Comparison and evaluation of resolved resonance region covariance representations

Journal of Nuclear Science and Technology (2023)

Hunter Belanger Amanda M. Lewis D. P. Barry

The covariance matrices for the evaluated resolved resonance region parameters are typically processed into a grouped covariance representation for use in uncertainty propagation studies. An alternative method for performing uncertainty propagation would be to use the resonance parameters covariance matrix to sample many realizations of resonance parameters, and then perform a simulation with each sample, employing the total Monte Carlo method. In this paper, we demonstrate that these two techniques can yield drastically different estimations of the uncertainty on keff. Furthermore, we provide reasoning as to why the grouped covariance approximation is a nonphysical approximation for the resolved resonance region, and how sampling resonance parameters is able to capture variations in the structure of the point-wise cross sections. Our recommendation is that the community move away from the grouped covariance approximation and towards a continuous energy representation, which could be generated by sampling resonance parameters, and ensure that the resonance parameter covariance matrices in evaluated libraries yield realistic grouped cross section uncertainties, regardless of group structure.

10.1080/00223131.2023.2279303

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Citations (1)

Neutron Transmission and Capture Measurements of ¹³³Cs from 0.01 to 600 eV

Nuclear Science and Engineering (2018)

R.C. Block J. A. Burke D. P. Barry N. J. Drindak G. Leinweber

Neutron capture and transmission measurements were carried out from 0.01 to 600 eV on both solid and liquid samples containing elemental cesium (133Cs). Only s-wave resonances were observed in these measurements. These data were analyzed for resonance parameters utilizing the SAMMY Bayesian analysis code to simultaneously fit both the capture and transmission data. Parameters were obtained for 31 cesium resonances up to 600 eV. The thermal capture cross section and capture resonance integral were determined. The thermal capture cross section is 10% larger than the ENDF, JENDL, and JEFF evaluated values but lies within the uncertainty of the most recent measurement by Yoon and Lee [New Phys.: Sae Mulli (Korean Phys. Soc.)., Vol. 61, p. 7 (2011)]. The capture resonance integral has a statistical 1σ error of 2% and lies 1.4σ above the JENDL value, 5.5σ above the ENDF value, and 3.9σ above the JEFF value. The s-wave strength function was determined.

Neutron capture

Nuclear data

Ultracold neutrons

10.1080/00295639.2018.1520526

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Citations (2)

A new 103Rh Unresolved Resonance Region evaluation

Annals of Nuclear Energy (2023)

D. P. Barry Amanda M. Lewis L.C. Leal Jesse Brown

Nuclear data

Nuclear fission product

R-matrix

Matrix (chemical analysis)

10.1016/j.anucene.2023.109751

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Citations (2)

Neodymium neutron transmission and capture measurements and development of a new transmission detector

D. P. Barry

Neodymium

Source

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Citations (15)

Neutron capture measurements and resonance parameters of dysprosium

The European Physical Journal A (2017)

Seung Gu Shin Yong Uk Kye W. Namkung M. H. Cho Yeong-Rok Kang

Dysprosium

10.1140/epja/i2017-12402-7

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Quasi-Differential Neutron Scattering in Zirconium from 0.5 to 20 MeV

Nuclear Science and Engineering (2013)

D. P. Barry G. Leinweber R.C. Block Timothy J. Donovan Y. Danon

High-energy-neutron-scattering experiments for elemental zirconium were performed at the electron linear accelerator facility at Rensselaer Polytechnic Institute. The scattering experiments were performed in the energy region from 0.5 to 20 MeV using the time-of-flight technique. The scattering system is composed of an array of eight EJ301 liquid scintillator detectors coupled to photomultiplier tubes. The detector array collects data simultaneously at various angles. The raw signals from each detector were digitized and transferred to a personal computer hard drive for storage. The digitized data were postprocessed, and pulse-shape analysis was performed to determine whether the pulse was the result of a gamma ray or a neutron being detected. The experimental results were compared with Monte Carlo transport calculations that simulated the experiment. This comparison was a way to benchmark several nuclear data libraries used in the Monte Carlo code. Ratios of the calculated data to the experimental data (C/E values) are presented and used to compare the nuclear data libraries. Results show that the experimentally observed scattering cross section is smaller than the one used in the evaluated libraries at energies between 10 and 20 MeV. For all energies and angles, the investigated nuclear data libraries agree with the experimental data to within 9%. Overall, the JEFF-3.1 and JENDL-4.0 libraries provide the best match to the experimental data.

Nuclear data

10.13182/nse12-1

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Citations (13)

Quasi-differential neutron scattering from 238U from 0.5 to 20 MeV

Annals of Nuclear Energy (2014)

A. Daskalakis Rian Bahran E. Blain B. McDermott S. Piela

10.1016/j.anucene.2014.07.023

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Citations (23)