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At least 1,063 records · Page 59

Pion photoproduction cross section at large momentum transfer

The Real Compton Scattering experiment was performed in Hall A at the Thomas Jefferson National Accelerator Facility. It was designed to measure, for Compton scattering and π 0 -photoproduction, the differential cross section over a range of kinematic points and the polarisation transfer to the proton at a single kinematic point. The full range of the experiment in Mandelstam variables t and s was 1.6-6.46 GeV 2 and 4.82-10.92 GeV 2 respectively with beam energies of 2-6 GeV. The motivation for the experiment is to test the cross section and polarisation transfer predictions of perturbative QCD versus that of predictions from Generalised Parton Distribution models. This thesis will give an overview of the pertinent theory, experimental setup in Hall A and the extracting of the π 0 -photoproduction cross section.

72 PHYSICS OF ELEMENTARY PARTICLES AND FIELDS↗

Measurement of the Elastic Ep Cross Section at Q2 = 0.66, 1.10, 1.51 and 1.65 Gev2

The nucleon form factors have been investigated by physicists for decades because of their fundamental importance. The world data of the proton magnetic form factor GMp has been focused on Q2 lower than 5 GeV2 and they have large uncertainties at higher Q2. Jefferson Lab experiment E12-07-108 aims to improve the accuracy of the e ? p elastic cross section to better than 2% over a Q2 range of 7 ? 14 GeV2. From 2015 to 2016, the e ? p elastic cross section was measured over a wide range of Q2 from 0.66 ? 12.56 GeV2 at the Thomas Jefferson National Accelerator Facility in Virginia, USA. An unpolarized electron beam was scattered o? a cryogenic hydrogen target and the scattered electron was detected in the high resolution spectrometers. This thesis focuses on the cross section calculations of the data taken in the spring of 2015, where Q2 = 0.66, 1.10, 1.51 and 1.66 GeV2. At Q2 = 0.66 GeV2, an uncertainty < 3% was achieved and < 5% was achieved for the other three Q2 at the moment. The results were compared with the world data and the good agreement provides confidence for the experimental measurements at higher Q2.

Wang, Yang↗

The Differential Cross Section and Λ Recoil Polarization from γδ -> Κ0(ρ)

Presented is the analysis of the differential cross section and Λ recoil polarization from the reaction γδ -> Κ0(ρ). This work measured these observables over beam energies from 0.90 GeV to 3.0 GeV. These measurements are the first in this channel to cover such a wide range of energies. The data were taken using the CEBAF Large Acceptance Spectrometer (CLAS) at Jefferson Laboratory (JLAB) along with a tagged photon beam. This analysis was completed by identifying events of interest that decayed into the final state topology of π-π+,π-&rho'(ρ). Through conservation of energy and momentum, the Κ0, Λ and missing mass of the spectator proton were reconstructed. Utilizing the same analysis techniques, the observables were measured on two different experiments with good agreement. Photoproduction of strange mesons from the neutron are difficult to measure, consequently there are only a few measurements of this kind. Despite that, these reactions supply essential complementary data to those on the proton. The differential cross sections and the recoil polarization extracted, span the region where new nucleon resonances have been found from studies of the reaction γρ -> Κ+Λ. Comparisons between the Κ+Λ and Κ0Λ cross section demonstrate that possible interference terms near 1900 MeV are less pronounced in the latter. This unexpected result inspired a partial wave analyses (PWA) to be fitted to the data. The fit solution shows that this measurement fostered an improvement on the knowledge of observed resonance parameters, necessary to understanding these excited states. The study of nucleon resonances is a key motivating factor since the resonance masses can be calculated from the theory of the strong nuclear force, called quantum chromodynamics, or QCD.

72 PHYSICS OF ELEMENTARY PARTICLES AND FIELDS↗

Generation of the Cross Section Library for PROTEUS

The cross sections for a high-fidelity neutron transport code PROTEUS can be generated in multiple ways. Multigroup cross sections in the ISOTXS format can be generated using the external codes such as MC 2 -3 and Monte Carlo codes such as Serpent and OpenMC. For the Monte Carlo codes, their multigroup cross section outputs should be converted to the ISOTXS format using a post processor named GenISOTXS developed by ANL.

73 NUCLEAR PHYSICS AND RADIATION PHYSICS↗

Updated Draft ASME Boiler and Pressure Vessel Code Case for Use of Alloy 617 for Construction of Nuclear Components for Section III Division 5

Early in the United States’ very high temperature reactor program, several candidate nickel alloys were considered for use in construction of the intermediate heat exchanger. Based primarily on technical maturity, a downselection was made to focus on Alloy 617. After this downselection, the primary goal of the research and development program was to develop sufficient information on the high temperature properties of the material to qualify it for construction of high temperature nuclear components in the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel (BPV) Code. Alloy 617 is a solid solution strengthened material with nominal Ni Cr Co Mo composition, originally developed for aerospace applications such as burner can liners for turbine engines by Huntington Alloys. (Huntington Alloys is now Special Metals Division of Precision Castparts, Inc.) The ASME BPV Code allows use of Alloy 617 for construction of non nuclear pressure vessels, and Alloy 617 is used in fossil fired power plants. Section III, Division 1, Subsection NB of the ASME BPV Code was developed for construction of nuclear components in light water reactors and allows use of ferritic materials up to 700°F and austenitic alloys up to 800°F. Subsection NH of Section III Division 1 was written to allow higher temperature construction with a primary focus on sodium cooled reactors. Recently, a new Division 5 of Section III was published specifically for high temperature reactors (regardless of the primary working fluid) and incorporates both Subsections NB and NH. There are only five alloys currently allowed for use in high temperature nuclear components: 2.25Cr 1 Mo and V modified 9Cr 1Mo steels, Types 304 and 316 stainless steels, and the high nickel austenitic Alloy 800H. This very sparse set of allowed materials is in contrast with the collection of more than 150 materials that are allowed for use in non nuclear pressure vessel construction. A draft Code Case to add Alloy 617 to the list of qualified alloys for use in high temperature nuclear design was submitted to ASME in the early 1990s, but it was withdrawn prior to formal Code action.

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS↗

Static Irradiated ALSEP Scrub Section

The INL is studying the impacts of gamma radiolysis on the ALSEP minor actinide extraction process. This process uses an organic solvent consisting of a neutral diglycolamide extractant, N,N,N’,N’ -tetra-2- ethylhexylglycolamide (T2EHDGA), and an acidic extractant 2-ethylhexylphosphonic acid mono-2- ethylhexyl ester (HEH[EHP]) dissolved in an aliphatic diluent. The actinides and lanthanides are coextracted from relatively high nitric acid and the actinides are selectively stripped using a carboxylic acid buffered aminopolycarboxylic acid solution. Previous investigations of the radiolytic degradation processes on the ALSEP process performed at the INL focused upon the extraction section of the flowsheet. Current efforts are concerned with examining the scrub section of the ALSEP flowsheet. This report describes the static irradiations performed during the current fiscal year in support of the test loop irradiations which will be conducted later in FY-2017, and documents completion of the level four milestone (M4FT- 17IN030102012) entitled “Static Irradiated ALSEP Scrub Section.

38 RADIATION CHEMISTRY, RADIOCHEMISTRY, AND NUCLEA↗

Lie groups of variable cross-section channel flow

This paper considers Lie groups of scaling transformations for the system of equations governing inviscid, compressible, quasi-one dimensional (quasi-1D) fluid flow in channels with variable cross-section. We determine the coupling between the admissibility of the group transformations and the equation of state (EOS) model used to close the system as well as the spatial and temporal dependence of the channel cross-section. The results presented extend prior group analysis performed in Ovsiannikov and Boyd et al. on the equations of gas dynamics for 1D flow. In the context of channel flow, the analysis in Ovsiannikov and Boyd et al. is only applicable for a very limited scope of channels, namely for channels possessing planar, cylindrical and spherical symmetry where the flow is truly 1D. To illustrate the extension achieved using the quasi-1D model, we consider the classical Noh problem set up in a channel with a variable area cross-section. First, a new set of canonical variables are derived using the admissible scaling transformations. Then, by re-expressing the governing equations of motion in terms of the new variables, a solvable system of ordinary differential equations (ODEs) is acquired. The resulting explicit solutions of the problem extend the previous results of Ramsey et al. to solutions of the Noh problem for quasi-1D flow.

71 CLASSICAL AND QUANTUM MECHANICS, GENERAL PHYSIC↗

Automated Selection of Electron Neutrinos from the NuMI beam in the MicroBooNE Detector and Prospects for a Measurement of the Charged-Current Inclusive Cross Section

We present a fully automated selection of NuMI beam produced electron neutrinos interacting in the MicroBooNE liquid argon time projection chamber operating at Fermilab. This analysis makes use of the Pandora reconstruction framework and subsequently a selection method developed specifically to select $ν_e$ and $\barν_e$ in data. The selection also utilizes one of liquid argon’s signature capabilities, distinguishing electron-like and photon-like electromagnetic showers using dE/dx in data, as well as scintillation light-based timing. The studies presented here demonstrate a closure test of calculating the inclusive cross using Monte Carlo, where the input Monte Carlo cross section matches the extracted Monte Carlo cross section. From this we forecast the prospects of a future $ν_e$ + $\barν_e$ cross section with MicroBooNE data.

46 INSTRUMENTATION RELATED TO NUCLEAR SCIENCE AND ↗

Measurement of Hard Exclusive Electroproduction of π 0 Meson Cross Section in Hall A of JLab with CEBAF at 12 GeV

A complete description of nucleon structure requires the simultaneous knowledge of both the spatial and momentum information of the ultimate constituents of the nucleon, the quarks and gluons. Generalized Parton Distributions (GPDs) provide such tools to describe nucleon structure. GPDs are measurable through hard exclusive processes like Deeply Virtual Compton Scattering (DVCS) and Deeply Virtual Meson Production (DVMP). GPDs can describe hard exclusive processes only if Bjorken factorization is achieved during the hard scattering process. While DVCS data have given hints of the factorization regime being attained, such hints have not been observed for DVMP data. Testing for factorization in DVMP processes is the topic of this thesis. Exclusive π 0 electroproduction has been measured by experiment E12-06-114 in Hall A of JLab. Cross sections have been measured at three fixed Bjorken- x ( x B ): 0.35, 0.48 and 0.6 in the Q 2 range 3 to 9 GeV 2 . In this document we present an analysis of a subset of the data: x B = 0.35 in the Q 2 range 3.1 to 4.5 GeV 2 . The different structure functions: unseparated cross section (σ T + ϵσ L ), longitudinal-transverse interference (σ LT ), transverse-transverse interference (σ TT ), and the polarized response (σ LT' ) terms were extracted. The data was compared to a transversity GPD model. The model fails to reproduce the data even though the order of magnitude is in agreement for both model and data. We observe a strong disagreement between the data and the model for σ LT in terms of both magnitude and the cross section sign. Our results are in a larger and wider Q 2 domain but they are in agreement with existing measurements.

Dlamini, Mongi↗

Measurement of Compton scattering cross section at a few GeV electron energy

Electron Compton scattering is the best known fundamental QED process, however, a precision measurement of its cross section for a beam energy above 1 GeV has been lacking up to now. An updated high precision measurement of the neutral pion lifetime via the Primakoff effect (PrimEx-II) experiment was performed in Hall B of Jefferson Lab in 2010. The experiment used small angle coherent photoproduction of π 0 ’s in the Coulomb field of a nucleus, i:e: the Primakoff effect, to determine the lifetime with a precision of less than 1:5% . It therefore requires thorough understanding of the underlying systematic uncertainties. To facilitate that data for well known electromagnetic processes were taken concurrently with the photoproduction data. This analysis pertains to measuring the Compton scattering cross section, which occurs with similar kinematics to the primary process. The combination of the well established theory for this process with large collected statistics allowed to extract this cross section with high precision in an energy region of 4-5 GeV for 12 C and 28 Si targets. The results of this analysis will be presented.

Ye, Li↗

Nuclear Data and Cross Section Testing Using ENDF/B-VIII.0

With the release of the Evaluated Nuclear Data File (ENDF)/B-VIII.0 library, nuclear criticality safety practitioners and engineers have access to the latest cross section sets available for their analyses. However, these cross sections must be rigorously tested and validated to ensure that the nuclear data are responsive to the needs of the individuals responsible for developing, implementing, and maintaining computational tools for criticality safety applications. Thus, the ENDF/B-VIII.0 library is tested and validated with a large collection of experiments that were vetted by the International Criticality Safety Benchmark Evaluation Project and made available in the International Handbook of Evaluated Criticality Safety Benchmark Experiments. A selection of benchmark experiments for use within the criticality safety community were prepared and reviewed within the Verified, Archived Library of Inputs and Data (VALID), which is maintained by the Nuclear Energy and Fuel Cycle Division at Oak Ridge National Laboratory. The performance of the ENDF/B-VIII.0 library is assessed by using VALID models of benchmark experiments with the beta 12 version of SCALE 6.3 KENO V.a and KENO-VI Monte Carlo codes. The performance is compared with the results obtained from with the ENDF/B-VII.1 library. This report considers multigroup (MG) and continuous energy (CE) formats of the ENDF/B-VIII.0 and -VII.1 libraries. The benchmark experiments within VALID that validate the ENDF/B-VIII.0 library cover 15 broad system categories by using a range of fissile materials, uranium enrichments, plutonium isotopic vectors, and mixed uranium/plutonium systems. These forms are represented as metals, solutions, or various arrays of rods or plates that cover a variety of neutron energy spectra: thermal, fast, mixed, and intermediate. Over 600 cases were considered for use with the KENO V.a and KENO-VI codes with the ENDF/B-VIII.0 library. The results of the Monte Carlo comparison of ENDF/B-VIII.0 to ENDF/B-VII.1 with both KENO V.a and KENO-VI indicate that there is a less than 0.53% Δk difference between the bias of calculated k eff from the expected values. The CE ENDF/B-VIII.0 library results in smaller magnitude biases than the ENDF/B-VII.1 data for HEU-MET-FAST, HEU-SOL-THERM, IEU-MET-FAST, LEU-SOL-THERM, PU-SOL-THERM, and U233-MET-FAST systems, while the MG results yielded smaller magnitude biases for HEU-MET-FAST, HEU-SOL-THERM, IEU-MET-FAST, LEU-COMP-THERM, LEU-SOL THERM, MIX-COMP-FAST, and U233-MET-FAST systems. Most notable are the adjustments to the plutonium and 233 U cross section data, which has resulted in noticeably lower biases in the ENDF/B VIII.0 results for the mixed, plutonium, and 233 U systems. Results of the sensitivity data file comparison generated from TSUNAMI-3D for selected VALID cases for the ENDF/B-VIII.0 library indicate a very high level of agreement with correlation coefficients of the effect of nuclear data uncertainty on k eff (the c k integral parameter) all above 0.99. This indicates that cases with the ENDF/B-VIII.0 library would see very similar responses to any nuclear data errors or change as those with the ENDF/B-VII.1 library.

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS↗

Measurement of the Inclusive Electron-Neutrino Charged-Current Cross Section in the NO$\nu$A Near Detector

This thesis describes the methods used to extract the inclusive \nue charged-current cross section in the \nova~near detector using data collected from November 2014 to February 2017, corresponding to an exposure of 8.09 $\times 10^{20}$ protons-on-target of a primarily neutrino beam. The near detector is located at Fermilab, 800~m from the primary target. The neutrino beam peaks near 2~GeV and is able to probe a variety of different neutrino-nucleus interactions through their final-state characteristics. The flux-integrated double-differential cross section is measured with respect to the final-state electron kinematics, as well as the total cross-section as a function of neutrino energy integrated over the same phase space used for the double-differential measurement.

72 PHYSICS OF ELEMENTARY PARTICLES AND FIELDS↗

VERA Enhancements for Cross Section Shielding and Geometry Capabilities

Two tasks were undertaken in FY22 that focus on VERA enhancements. The first task involved improvements to the new cross section shielding capability that was added to VERA in FY21. This cell-based capability solves the slowing down problem for each pin cell using Dancoff factors calculated from the whole-core problem. The Dancoff factors are determined for each subgroup level for important sets of materials such as fuel rods, control rods, fuel rods loaded with gad, etc. The cross-section shielding is then performed for each cell using a 1D cylindrical collision probabilities (CP) calculation to obtain the equivalence cross sections required for the core transport calculations. The advantage of this method over the whole-core subgroup calculations is efficiency, since far fewer sweeps of the entire core are required.

22 GENERAL STUDIES OF NUCLEAR REACTORS↗

Study of a Proposed fissionTPC Measurement of 233 U(n,f)/ 235 U(n,f) Cross Section Ratio

A review of the available 233 U( n, f )/ 235 U( n, f ) cross section ratio data compared to the ENDF evaluation in the fast neutron energy range, 0.1–20 MeV, shows that discrepancies exist between some of the various measurements and the evaluation. The discrepancies vary and a function of incident neutron energy and range between 1–5%. In this document we review two potential options for performing new measurements of the cross section ratio to potentially resolve these discrepancies. The two options are compared and contrasted in terms of measurement accuracy and cost. The first option would utilize the fissionTPC, which was designed specifically to achieve measurement uncertainties of better than 1% to resolve a similar data–evaluation discrepancy in the 239 Pu( n, f ) cross section. While this would seem to be an ideal option in this case also, there are challenges. The fissionTPC is a complex instrument and the cost of maintenance and operations are significant. Furthermore, some of the fissionTPC equipment is nearing the end of its useful life which presents a risk to completion of a measurement campaign. The second option is to use a dual-fission chamber, which is the more traditional approach to these types of measurements. The cost is estimated to be about half that of a fissionTPC measurement, while the much simpler design of the detector reduces overall risk. The trade-off is the measurement uncertainty, which would be on order of 1–3% with a careful measurement and analysis. This uncertainty however may not be good enough to fully resolve the discrepancies. The objective of a new measurement would be the improvement in the ENDF evaluation with the end goal of improving the accuracy of models and simulations at the end of the nuclear data pipeline. An understanding of the sensitivity of these models to the data uncertainties would help guide the choice of measurement techniques.

73 NUCLEAR PHYSICS AND RADIATION PHYSICS↗

Review of capture cross sections relevant for intentional nuclear forensics

The NA-22 Intentional Forensics Venture is developing a system for tagging nuclear fuel using various methods of information encoding. One of the main methods under development is the insertion of isotopically enriched tracers into the fuel. In order to aid in the understanding of the neutronic performance of these taggants, we assess the quality of the nuclear data underpinning simulations, which are driven by the neutron-capture cross sections. We present these cross sections of naturally occurring isotopes of the elements provided in the neutron sublibrary of the planned ENDF/B-VIII.1 Feb. 2023 library release. We make this assessment using a rubric designed for this effort, which quantifies orthogonal features related to the overall quality. The quality metric highlights 6 aspects: experimental data, resonance evaluations, integral metrics, covariances, fission products, and documentation. We focus on energy ranges relevant for reactor applications. We also discuss additional sources for new, high-quality cross-section data that may be utilized on the time scale of the venture, including existing global data, new experiments, and computational methods. Finally, overall outlook is presented with conclusions.

73 NUCLEAR PHYSICS AND RADIATION PHYSICS↗

Status of the muon neutrino charged-current zero mesons cross section measurement in the NOvA near detector

NOvA is a long-baseline accelerator neutrino experiment at Fermilab whose physics goals include precision neutrino oscillation as well as cross-section measurements. We present the status of the measurement of muon neutrino charged-current cross section with zero mesons in the final state at the NOvA near detector. This measurement will be made with respect to the kinematics of the final state particles. Our chosen interaction channel is especially sensitive to quasielastic and meson exchange current interactions and will provide a handle for constraining the cross section systematic uncertainties in oscillation analyses in current and future experiments. For particle identification, we use a convolutional neural network (CNN) trained on individual particles simulated in the NOvA near detector that allows us to select the desired signal while reducing the potential bias from neutrino interaction modeling. Charged pion background constraining is further improved via Michel electron tagging.

72 PHYSICS OF ELEMENTARY PARTICLES AND FIELDS↗

Physics of Neutrino Oscillations and Neutrino Cross Sections using the NOvA Experiment

NOvA is a long-baseline accelerator-based neutrino experiment based in the US. NOvA uses an intense neutrino beam produced at Fermilab’s accelerator complex to make physics measurements of neutrino oscillations, neutrino cross sections, and much more. For its physics goals, NOvA uses two functionally-identical detectors. The Near Detector (ND) is situated at Fermilab, 1 km from the neutrino target and the Far Detector (FD) is located at Ash River, MN, a distance of 810 km from the neutrino source. The ND receives a high statistics neutrino flux which gives a unique opportunity for high-precision neutrino cross-section measurements and is used as a control for the oscillation analyses. The FD is used to analyze the appearance and disappearance of the neutrinos arriving from the Fermilab. The purpose of the oscillation analysis is to understand the dominance of matter over antimatter in the universe, to resolve the ordering of neutrino masses, and to resolve the octant of the neutrino mixing angle theta23. In this talk, I will give an overview of the NOvA experiment. I will also talk about the status of the NOvA’s cross-section physics program and the latest results from the oscillation analyses. I will also talk about the future prospects of the experiment.

72 PHYSICS OF ELEMENTARY PARTICLES AND FIELDS↗

Evaluation of Thermal Neutron Scattering Cross Section of Uranium Silicide with Ab Initio Lattice Dynamics

Uranium silicide (U 3 Si 2 ) is a candidate material for the high-density nuclear fuel in commercial light water reactors [1], [2]. Its higher uranium density, 11.3 g-U/cm3, compared to that of uranium dioxide (UO 2 ), 9.7 g-U/cm3, can improve the performance of a nuclear reactor while using low enriched uranium (LEU) and diversify the choice of cladding materials [1]–[3]. It also has a higher thermal conductivity than UO 2 , which can reduce the thermal stress on the material caused by a temperature gradient across the fuel pellet and provide a larger margin for some postulated accidents [1], [2], [4]. Furthermore, compared to U3Si, another high-density fuel candidate, it has better resistance to in-pile swelling due to less irradiation-induced rapid amorphization [1], [3]. Corresponding to its importance in nuclear engineering, many previous studies have reported the properties of U3Si2. Experiments showed that U 3 Si 2 is a paramagnetic (PM) metal, where a slight linear increase in magnetic susceptibility was measured with increasing temperature [5], [6]. In addition, thermodynamic quantities such as thermal expansion coefficient, heat capacity, and thermal conductivity were experimentally determined over a wide temperature range [1], [7], [8]. In several computational studies, ab initio atomistic simulations based on density functional theory (DFT) were performed to calculate various properties including elastic constants, electronic density of states (DOS), and phonon dispersion curves [9]–[12]. Nevertheless, thermal neutron scattering cross sections, which are critical to the prediction of the parameters in reactor physics that are ultimately related to reactor criticality, have not yet been evaluated for U3Si2. The scattering cross section can be calculated from the phonon DOS, or the energy spectrum of lattice vibrations, of the crystalline system [13], [14]. However, there is also no experimental data available for the phonon DOS of U 3 Si 2 . While some computational studies reported the phonon DOS and/or dispersion curves from ab initio simulations [9]–[12], the accuracy cannot be guaranteed because it is unclear whether the spin-polarization behavior of PM U 3 Si 2 was properly described. In the present study, the thermal neutron scattering cross section for U 3 Si 2 is evaluated for the first time by calculating the phonon DOS for U3Si2 from ab initio lattice dynamics (AILD) simulations based on DFT. First, U 3 Si 2 is modeled based on the experimental structure, and AILD simulations are performed on the modeled U3Si2 to optimize the structure. Next, AILD simulations are performed for supercells with atomic displacement to calculate Hellmann-Feynman forces. Based on the calculated forces, partial phonon DOSs for U and Si are obtained, and the thermal neutron scattering law (TSL) for U 3 Si 2 is finally evaluated. To verify the accuracy of the calculations in the present study, the calculation results are compared with experimental data on the structure and heat capacity of U3Si2 [1], [7], [8], [15].

Geometry Optimization↗