dataesr/scientific-paragraphs-categorization huggingface dataset:
The total cross section of each isotope contained in the nuclear data libraries has been converted to transmission data to reproduce the experiment using the following equation: T = e -nσ tot ( 1 ) where T is the transmission coefficient, n is the areal density of the sample and σ tot is the total cross section. The impact of these libraries in the MYRRHA MOX critical core model has been evaluated by substituting the whole or individual reactions of JEFF-3. 2, by the ones in ENDF/B-VII. 1 or JENDL-4. 0. The cross sections have been pre-processed using the NJOY processing system  [20] , while for the substitution of the data for individual reactions from different libraries the SANDY code  [21]  has been applied.
208 Pb Two transmission measurements were carried out by Carlton et al. [22]  and Harvey et al. [23]  at the ORELA facility with a 200 m flight path, using a 208 Pb enriched sample with an areal density of 0. 18594 at/b and 6 Li glass detectors and a 208 Pb enriched sample with an areal density of 0. 16882 at/b and Ne-110 plastic scintillators detectors, respectively. No information about the enrichment of the samples is provided in EXFOR. The ORELA facility is well characterized, including the resolution function. Carlton's experimental dataset has better experimental resolution in the MYRRHA-relevant energy range. In Fig. 3 , Carlton's transmission dataset is compared with the nuclear data evaluations. Perfect agreement with experimental data is found until the end of the resolved resonance region (RRR) -1 MeV-for all evaluations.
209 Bi Harvey et al. [24]  transmission data is the best documented data set available in the energy range of interest. The TOF experiment was performed at the ORELA facility in a 200 m flight path using a Bi sample with an areal density of 0. 5651 at/b and Ne-110 plastic scintillator detectors. A comparison of the evaluated nuclear data libraries against experimental data is shown in Fig. 4. JEFF-3. 2, ENDF/B-VII. 1 and JENDL-4. 0 libraries have a good agreement with experimental data in the RRR (10 µeV -200 keV). In the URR and fast energy range, JEFF-3. 2 and ENDF/B-VII. 1 are coincidental with Harvey's data points while the JENDL-4. 0 total cross section is fitted. The results of differences in MOX critical core k e f f for 209 Bi neutron induced reaction cross sections from different libraries are shown in Table  3.
Conclusions The sensitivity and uncertainty analysis of the MYRRHA MOX critical core design has been presented, identifying the major sensitivity coefficients, the uncertainty in k e f f and the contribution of the most relevant quantities to the k e f f uncertainty, using different codes and nuclear data libraries. Differences smaller than 4% have been obtained for the sensitivity coefficients. However, considerable differences have been observed between k e f f uncertainties calculated using different covariance matrix evaluations. A comparison of experimental data and evaluated nuclear data libraries for 208 Pb and 209 Bi has been carried out. Existing experimental transmission data available in the EXFOR database has been identified and compared against the JEFF-3. 2, ENDF/B-VII. 1 and JENDL-4.
0 evaluations. JENDL-4. 0 has been found to be the most accurate evaluation for both isotopes in the MYRRHArelevant energy range. Finally, ENDF/B-VII. 1 and JENDL-4. 0 nuclear data libraries have been compared using the MYRRHA MOX fueled critical core model. Different parts of data (energy regions and/or reactions) in reference JEFF-3. 2 files have been substituted by corresponding data from the other libraries and effects on the system multiplication factor have been observed.
Acknowledgments The authors are very grateful to the  CNRS (Steeve Zozor)  and the  Junta de Andalucía  and the  MINECO-FEDER  under the grants  FIS2014-54497  and  FIS2014-59311P  (J. S. D. ) for partial financial support. Moreover, they are grateful for the warm hospitality during their stays at  GIPSA-Lab of the University of Grenoble-Alpes (D. P. C. ) and Departamento de Física Atómica, Molecular y Nuclear of the University of Granada  (S. Z. ) where this work was partially carried out. authorcontributionsThe authors contributed equally to this work.
The WZ boson pair production at 13 TeV is measured using the ATLAS detector. Leptonic decays of the W and Z bosons to electrons and muons are considered using 2015 and 2016 data that correspond to a total integrated luminosity of 13. 3 fb -1. The differential cross-section as a function of jet multiplicity is also measured along with the charge-dependent W + Z and W -Z cross-sections and their ratio. Also, the integrated fiducial cross-sections ratio, measured at center-of-mass energies of 8 TeV and 13 TeV, is calculated. Finally, limits on anomalous triple gauge couplings are derived.
Results The measured fiducial cross-sections in the four channels are combined using a χ 2 minimisation method  [9] [10] [11]. The results presented in the following represent the first two measurements in the new energy regime of 13 TeV. They correspond to the 2015 dataset with 3. 2 fb -1 and to the 2016 dataset with 10. 1 fb -1 , giving a total integrated luminosity of 13. 3 fb -1. Unless otherwise stated, the results shown will be the ones obtained with the total integrated luminosity of 13. 3 fb -1.
Integrated cross-sections Figure  3  shows the ratio of the measured fiducial cross-sections per channel over the theoretical predictions using Powheg+Pythia at NLO QCD. The combined measured fiducial cross-section is: σ f id. W ± Z→ ν = 66. 2 ± 1. 8(stat. ) ± 3. 6(sys. ) ± 2. 1(lumi. ) f b. (1) EPJ Web of Conferences The SM NLO prediction from Powheg+Pythia is 53. 4 +1. 6 -1. 2 (PDF) +2. 1 -1. 6 (scale) f b, which is obtained using the CT10 PDF set and by setting the dynamic QCD scales µ R and µ F to m WZ /2. Using the 3. 2 fb -1 of the 2015 dataset, the combined fiducial cross-section was extrapolated to the total phase-space resulting: σ tot. W ± Z = 50. 6 ± 2. 6(stat. ) ± 2. 0(sys. ) ± 0. 9(th. ) ± 1. 2(lumi. )pb The SM NLO prediction calculated with Powheg+Pythia is 42. 4 ± 0. 8(PDF) ± 1.
6(scale)pb. A recent NNLO calculation  [12]  yields 48. 2 +1. 1 -1. 0 (scale)pb, a result which is in better agreement with the measurement. Also, with the 2015 dataset the ratio of the W ± Z production cross-section at the two centre-of-mass energies of 13 TeV over 8 TeV is also calculated and it is where all uncertainties are treated as uncorrelated and the result being in good agreement with the SM prediction from Powheg+Pythia of 1. 78±0. 03. Finally, the ratio of W + Z to W -Z is calculated σ f id. W + Z→ ν σ f id. W -Z→ ν = 1. 39 ± 0. 14(stat. ) ± 0. 03(sys. ) ± 0. 06(lumi. ) The result is shown in Figure  4. It is dominated by the statistical uncertainty and it is compared to the SM prediction from Powheg+Pythia of 1. 47 +0. 03 -0. 06.
Differential distributions The differential cross-section as a function of the Z-boson p T as well as the transverse mass of the WZ-system is presented in Figure  5. It is obtained by correcting for detector effects (such as finite resolution, limited acceptance and imperfect efficiency) as well as for QED FSR effects using a Bayesian iterative method  [13, 14]. A response matrix, accounting for bin migration effects between the reconstructed and particle-level distributions, is obtained using Powheg+Pythia. The unfolded distributions are compared to the predictions from Powheg+Pythia and Sherpa, showing a very good description of the data. Using the 2015 dataset the differential cross-section as a function of the jet multiplicity was also calculated and it is presented in Figure  6. The same iterative Bayesian method was used and the unfolded result is compared to the predictions from Powheg+Pythia and Sherpa.
The presence of aTGCs would affect the integrated cross-section and is expected to increase the yields of the higher bins of the aforementioned distribution. Figure  6. Distribution of m WZ T in the sum of all channels with the same binning as used for the calculation of aTGC confidence intervals. The points correspond to the data and the histograms to the expectations of the different SM processes. The shaded violet band its estimated total uncertainty  [4]. The 95% confidence intervals are derived using the frequentists approach by using a profile likelihood that incorporates all systematic uncertainties as nuisance parameters. The cutoff scale is set to Λ co = ∞ (no cutoff), as the current sensitivity is well within the unitarisation constraints. To improve the sensitivity the confidence intervals are also derived by combining the 8 TeV and 13 TeV datasets.
[4]erved and expected number of events after the WZ inclusive selection in each of the four final-state topologies. The observed WZ events are selected from the dataset collected during 2015 and 2016 that corresponds to an integrated luminosity of 13. 3 fb -1. The expected number of WZ events from Powheg+Pythia and the estimated number of background events from other processes are detailed. The signal WZ sample is normalised to NNLO cross section. The uncertainties quoted are only statistical[4].
Methods STM measurements. The experiments were performed in an ultra-high vacuum STM operated at 2. 5 K. A clean Cu(100) surface was prepared by repeated cycles of Ar + sputtering and annealing up to 800 K at a base pressure of 2 × 10 -10 mbar. Nickelocene molecules were deposited from a crucible onto the cold copper surface (below 80 K) at a rate of 0. 025 ML/min resulting in a sub-monolayer coverage. Directly after molecular deposition, the sample was inserted in the STM. Analysis of STM data were performed with the WSxM software  60. Calculation details. Calculations were carried out using two DFT packages. VASP  [61] [62] [63] [64] [65] [66]  has been used to explore the adsorption of the Nc molecule on a STM tip modeled by a Cu(100) surface with a Cu adatom acting as a monoatomic tip apex.
The valence-electron wavefunctions were expanded in a basis set of local orbitals in SIESTA. A double-ζ plus polarization (DZP) basis set was used to describe the Nc molecule and surface-atom electrons. Diffuse orbitals were used to improve the surface electronic description and a single-ζ plus polarization basis set for the copper electrodes. The use of a DZP basis set to describe the adsorbate states is mandatory in order to yield correct transmission functions  70. The k-point sampling was converged at 3 × 3, although the sampling was 11 × 11 for the transmission calculations. These transport calculations were carried out from firstprinciples with a method based on non-equilibrium Green's functions combined with DFT as implemented in the TranSIESTA package  68. The Ni pseudopotential used in the SIESTA calculations was extracted from reference  71   3c ) and the thin line to the contact configuration (Fig.
Acknowledgements This work has been supported by the  Agence Nationale de la Recherche  (Grant Nos. ANR-13-BS10-0016 ,  ANR-11-LABX-0058   NIE ,  ANR-10-LABX-0026 CSC ) the  ANPCyT  project  PICT  Bicentenario No. 1962 , the  CONICET  project  PIP 0667 , and the  UNR  project  PID ING235. We acknowledge computer time provided by the  CCT-Rosario Computational Center  and the  Computational Simulation Center (CSC)  for Technological Applications, members of the  High Performance Computing National System (SNCAD, MincyT-Argentina). Financial support from  MINECO   MAT2015-66888-C3-2-R  and  FEDER  funds is also gratefully acknowledged.
Both current and thermal gradient were applied along the length of the ribbons. The electrical resistivity was measured by a four-probe AC method, using an SRS Model SR83 Lock-in Amplifier with a low-frequency current of 5 mA (77 Hz) applied to the sample. The thermopower was measured by a slow AC technique (ca. 10 -2 Hz), the voltage across the sample and gold leads being measured with a Keythley 181 nanovoltmeter. The oscillating thermal gradient was kept below 1 K and was measured by a Au-0. 005 at % Fe versus chromel thermocouple. The absolute thermopower of the sample was obtained after correction for the absolute thermopower of the gold leads (99. 99% pure gold) by using the data of Huebener  [57]. The experimental uncertainties on the electrical resistivity and thermopower are estimated to be 7% and 5%, respectively.
Acknowledgments: This work was supported by  Electricité de France R&D  through the  CIFRE (Conventions Industrielles de Formation par la Recherche ), convention No. 2011/1329. The authors thank  Pascal Dalicieux ,  Philippe Baranek  and  Laurent Legras  from  Electricité de France. They are also grateful to  Jaafar Ghanbaja  for his support in HRTEM investigations.
The poloidal asymmetry has been associated to the presence of superthermal electrons [1] while the toroidal one has been less clearly identified as due to the small toroidal extension of the limiters. To account for the 2D deposition nature of heat load on the surface of the employed limiters, a simple 3D code has been developed to evaluate heat flux from temperature data. In this way at the deeper limiter insertions a heat flux decay length of about 2 mm and 2. 5 mm has been evaluated in electron and ion drift sides. Modelling of the evaluated heat fluxes has been done using the SOLEDGE2D-EIRENE edge code  [2]. This fluid code is well suited for the RFX-mod wall limiter configuration because, thanks to the implemented penalization technique, the computational domain can be extended up to the entire first wall.
Furthermore in RFX-mod case the knowledge of the transport parameters at the plasma edge is a necessary element for the design of the foreseen device upgrade in which plasma boundary will play a fundamental role  [6]. In this paper we present the first attempt to study the transport in the plasma Edge/SOL of the RFX-mod device analysing the power load on an insertable graphite limiter and modelling it with a 2D edge fluid code. To evaluate the power we have measured the temperature evolution of the limiter surface with an infrared camera. To extract quantitative information on plasma transport from the computed heat flux we have used the SOLEDGE2D-EIRENE edge fluid code  [2]. In the next sections we will describe the experimental setup first, briefly the method to compute the heat flux from the tem- perature measurement, then we will analyse the measurements in terms of global plasma parameters and finally we present the results of the edge modelling.
The results of the code have been compared with those of the THEODORE code for a 1D (on surface) case and the two gave results in agreement. For one experimental case the TtoP3D computed heat flux has been used in an ANSYS model of the limiter, to compute the surface temperature obtaining a good agreement with the measured one. An example of the computed heat flux for an RFX-mod pulse is shown in Fig. 4. One simple parameter that characterizes the edge transport is the decay length of the plasma parallel heat flux. We can compute it after converting the heat flux perpendicular to the limiter surface ( P S ) to those parallel ( P D ) and perpendicular ( P ⊥ ) to the magnetic surfaces. In the general case the heat flux on surface is related to the plasma heat fluxes by the relation: P S = sin αP + cos αP ⊥ where α is the angle between the magnetic surface and the limiter surface.
Edge modelling To get some insight into the plasma transport properties of the edge and of the SOL, the code SOLEDGE2D-EIRENE has been used  [2]. It is a 2D transport code with a multi-species plasma solver coupled to EIRENE for neutrals; it solves the continuity equations for densities, parallel velocities, temperatures and electric potential. One of the main advantages of SOLEDGE2D code is the ability to simulate the plasma up to the first wall (FW)  [2]. In other codes, e. g. , UEDGE  [21]  and EDGE2D  [22]  the computational domain usually does not extend up to the FW or, like for the SOLPS code, custom solutions are adopted to deal with the FW  [23, 24]. Instead in SOLEDGE2D the FW is managed by the penalization method  [25, 26]  , which extends the solution of fluid equations inside the wall and controls the sharp gradients which form at the wall interface by the penalization parameter.
[29]  and there in); thermal conductivity has been assumed equal between electrons and ions ( χ e L χ i ) which is also a strong assumption considering the uncertainties in the nature of the transport at the edge/SOL. Due to the previously described limitation in terms of available measurements and of modelling assumptions, the final aim of the comparison was not to get exact values and profiles for the transport parameters but Please cite this article as: P. formed with the ASTRA code from profiles measurements in RFXmod  [30, 31]  , but they did not provide the heat flux profiles measured on the limiter. Instead, in order to match also the heat flux profiles, it is necessary to assume D and χ reduced by a factor of about ten in the SOL with respect to plasma edge. Fig. 7  shows the results of two SOLEDGE2D-EIRENE simulations of a low density 700 kA discharge with the two transport coefficient profiles: constant in the edge/SOL regions (blue) and with ten times reduction of D and χ in the SOL (red).
Conclusions In RFX-mod for the first time the edge transport has been analysed and modelled by means of thermography measurements and edge fluid code. The measurements confirmed the presence of increased heat flux in the direction of the electron drift side at low density. This result is in agreement with previous RFP findings, the novelty of this measurement is the identification of the density threshold above which the asymmetry disappears. The agreement of such threshold with that observed for the achievement of Quasi Singles Helicity states in RFX-mod  [5]  could be a coincidence but could also be the indication that, as described in the KDT theory, at low density a fraction of the poloidal current is due to superthermal electrons, reducing the demand on the MHD dynamo. The modelling performed with the SOLEDGE2D-EIRENE code has shown that the transport is drastically reduced in the SOL region compared to the edge one.
In this study, variance reduction options of the TRIPOLI-4 code were used on the NAIADE 1 light water shielding benchmark. This benchmark document is available from the OECD/NEA SINBAD shielding benchmark database. From this benchmark database, a simplified NAIADE 1 water shielding model was first proposed in this work in order to make the code validation easier. Determination of the fission neutron transport was performed in light water for penetration up to 50 cm for fast neutrons and up to about 180 cm for thermal neutrons. Measurement and calculation results were benchmarked. Variance reduction options and their performance were discussed and compared.
To develop its application on nuclear decommissioning activities, both experimental and computational benchmarks are being developed and performed. For the neutron activation calculation of shielding and structure materials of nuclear facilities, the knowledge of 3D neutron flux map and the energy spectra must be first investigated. In this kind of neutron deep penetration calculation in shielding, variance reduction techniques are necessary in order to reduce the uncertainty of the Monte-Carlo calculations  [3, 4]. Different water shielding benchmarks are available from the OECD/NEA SINBAD database. The NAIADE 1 water benchmark was essential because of its important water thickness  [5, 6]. In this study, the fission neutron deep penetration in water shielding was investigated with TRIPOLI-4 code for NAIADE 1 water benchmark.
At the end of this initialization step, the importance map from this learning-by-simulation procedure helps guiding the neutron transport in all next sets of neutron histories. The "monitoring" option was used by default in the TRIPOLI-4 variance reduction run. The adjustments of the importance map were performed from energy group to energy group by taking advantage of statistics on discrepancies between particle weights and reference weights given by the importance map, when particles slowing down in energy from group to group. Of course the performance of the associated variance reduction depends importantly on the input data dedicated to the INIPOND module. The options for displaying of collision points and iso-importance curves were helpful to understand the particle propagation in water and useful to improve the importance map calculation.
V. Results TRIPOLI-4 calculation results are divided in three parts. The first part shows the intermediate graphic results. These results are helpful to understand the variance reduction effects on fission neutron transport in water, to adjust the variance reduction parameters, and to improve the calculation performance. The second part presents the numerical calculation results of the NAIADE 1 water benchmark including the fast neutron and thermal neutron equivalent flux as a function of water shielding thickness. The third part shows the variance reduction performance results. The graphic intermediate results including the collision sites maps and the importance maps generated in this study are presented in Fig. 4  and 5. Two different input data sets for the INIPOND variance reduction module, one with discrete attractors and the other with the spherical attractor surface  [7] , were applied to qualitatively demonstrate the variance reduction effects.
2012; Busquet et al. 2014). To conclude, within the context of the study of iCOMs, the advantages of the L1157-B1 laboratory are twofold: (i) the source is not di- Send offprint requests to: C. Codella, e-mail: codella@arcetri. astro. it rectly heated by the protostar, which is 0. 08 pc away, and (ii) solid species in dusty icy mantles have been injected into the gas phase due to a jet-induced shock and consequently sputtering (e. g. Bachiller et al. 2001). L1157-B1 is one of the targets of the SOLIS 1  (Seeds Of Life In Space; Ceccarelli et al. submitted, hereafter Paper I) IRAM NOEMA (NOrthern Extended Millimeter Array) large program to investigate iCOM formation during the early stages of the star forming process. In this Letter we report the first high spatial resolution NH 2 CHO image and comparison with the acetaldehyde (CH 3 CHO), which allow us to constrain how gas phase chemistry matters for the formation of NH 2 CHO.
Once in the gas, the two species undergo reactions that destroy them (Fig. 3 ). Specifically, both acetaldehyde and formamide are attacked by the most abundant gaseous ions, namely H 3 O + , H 3 + and HCO + , which produce protonated acetaldehyde and protonated formamide, respectively. Protonated formamide rapidly recombines with electrons and forms back formamide in only 20% of cases, according to the KIDA database (formamide is not present in the UMIST database). Similarly, the recombination of protonated acetaldehyde produces acetaldehyde in only 9% of electron recombinations. While the rate and products of the protonated formamide recombination are guessed, those of acetaldehyde, from the UMIST database, are measured  (Hamberg et al. 2010 ). However, since the two species are destroyed by the same ions, even if the branching ratios of the formamide recombination in the KIDA database are wrong, what matters is the percentage of electron recombinations that give back formamide, which is certainly not unity.