scholarly journals New evaluation of general purpose neutron data for stable W-isotopes up to 200 MeV

2020 ◽  
Vol 239 ◽  
pp. 11002
Author(s):  
A.Yu. Konobeyev ◽  
U. Fischer ◽  
P.E. Pereslavtsev ◽  
S.P. Simakov
Keyword(s):  
Cross Sections ◽  
Neutron Transport ◽  
Production Cross ◽  
Neutron Cross Section ◽  
Evaluation Process ◽  
General Purpose ◽  
Gas Production ◽  
Nuclear Model ◽  
Data Format ◽  
Cluster Emission

In the frame of the Power Plant Physics and Technology of EUROfusion, new evaluations of general purpose neutron cross-section data were performed for the 180,182,183,184,186W isotopes covering the neutron energy up to 200 MeV. A special version of the TALYS nuclear model code implementing the geometry dependent hybrid model supplied with models for the non-equilibrium cluster emission was applied for calculations of the nuclide production and the energy distribution of the emitted particles. The parameters of the GDH model were properly estimated using measured data for individual tungsten isotopes. The neutron cross-sections were evaluated making use of available experimental data, systematics including estimated A-dependence of components of gas production cross-sections, and covariance information produced as part of the evaluation process. The BEKED code package, developed at KIT, was applied for calculations of co-variances using a dedicated Monte Carlo method. The evaluated data were processed into standard ENDF data format using the TEFAL code and the FOX module of the BEKED system. The evaluated data files were checked for errors and inconsistencies, processed with the NJOY code into ACE data format, and benchmarked against available integral experiments with MCNP neutron transport calculations.

scholarly journals Modeling of the ORNL PCA Benchmark Using SCALE6.0 Hybrid Deterministic-Stochastic Methodology

2013 ◽  
Vol 2013 ◽  
pp. 1-9 ◽  
Author(s):  
Mario Matijević ◽  
Dubravko Pevec ◽  
Krešimir Trontl
Keyword(s):  
Cross Sections ◽  
Neutron Transport ◽  
National Laboratory ◽  
General Purpose ◽  
Monte Carlo Code ◽  
Oak Ridge ◽  
Benchmark Data ◽  
Selection Of ◽  
Good Agreement ◽  
Reactor Dosimetry

Revised guidelines with the support of computational benchmarks are needed for the regulation of the allowed neutron irradiation to reactor structures during power plant lifetime. Currently, US NRC Regulatory Guide 1.190 is the effective guideline for reactor dosimetry calculations. A well known international shielding database SINBAD contains large selection of models for benchmarking neutron transport methods. In this paper a PCA benchmark has been chosen from SINBAD for qualification of our methodology for pressure vessel neutron fluence calculations, as required by the Regulatory Guide 1.190. The SCALE6.0 code package, developed at Oak Ridge National Laboratory, was used for modeling of the PCA benchmark. The CSAS6 criticality sequence of the SCALE6.0 code package, which includes KENO-VI Monte Carlo code, as well as MAVRIC/Monaco hybrid shielding sequence, was utilized for calculation of equivalent fission fluxes. The shielding analysis was performed using multigroup shielding library v7_200n47g derived from general purpose ENDF/B-VII.0 library. As a source of response functions for reaction rate calculations with MAVRIC we used international reactor dosimetry libraries (IRDF-2002 and IRDF-90.v2) and appropriate cross-sections from transport library v7_200n47g. The comparison of calculational results and benchmark data showed a good agreement of the calculated and measured equivalent fission fluxes.

e+e- HADRON PRODUCTION CROSS SECTIONS AT BELLE

2014 ◽  
Vol 35 ◽  
pp. 1460407
Author(s):  
JASON D. CRNKOVIC ◽  
Keyword(s):  
Cross Sections ◽  
Solid Angle ◽  
Standard Model Prediction ◽  
Production Cross ◽  
General Purpose ◽  
Final State ◽  
Belle Detector ◽  
Electron Positron Annihilation ◽  
Electron Positron ◽  
The Standard Model

A number of production cross sections for electron-positron annihilation to a hadronic final state have been measured using the Belle dataset, which is possible given the general purpose design of the Belle detector and its large solid-angle coverage. The cross section measurements predominantly fall above 3 GeV, which still leaves the opportunity for using the dataset to systematically measure cross sections below 3 GeV. These low-energy cross sections are important for improving the precision of the Standard Model prediction for the muon anomalous magnetic moment.

scholarly journals Neutron inelastic scattering of 232Th: measurements and beyond

2019 ◽  
Vol 211 ◽  
pp. 03005 ◽  
Author(s):  
Eliot. Party ◽  
Catalin. Borcea ◽  
Philippe. Dessagne ◽  
Xavier. Doligez ◽  
Grégoire. Henning ◽  
...  
Keyword(s):  
Cross Sections ◽  
Gamma Spectroscopy ◽  
Production Cross ◽  
Reactor Core ◽  
Neutron Cross Section ◽  
Theoretical Models ◽  
Data File ◽  
Prompt Gamma ◽  
Incident Neutron ◽  
Total Uncertainty

Gamma production cross sections have been obtained for 81 transitions in 232Th from (n,n’γ), 11 in 231Th from (n,2nγ) and 7 in 230Th from (n,3nγ) reactions using prompt gamma spectroscopy. Incident neutron energies were determined using the neutron time-of-flight technique. Sources of uncertainty have been examined and their correlations have been computed. Total uncertainty on cross sections ranges from 4 to 20%. Obtained cross sections are in agreement with prior experiments, but are not well reproduced by the TALYS 1.8 reaction code using default parameters. During analysis, discrepancies between our findings and the Evaluated Nuclear Structure Data File (ENSDF) were noted. Future work related to the present experiment includes: improving theoretical models, quantifying the influence of the 232Th inelastic neutron cross section on reactor core parameters, and conducting additional measurements.

scholarly journals Forming molecular states with hadronic rescattering

2022 ◽  
Vol 58 (1) ◽  
Author(s):  
Philip Ilten ◽  
Marius Utheim
Keyword(s):  
Cross Section ◽  
Cross Sections ◽  
Production Cross ◽  
General Purpose ◽  
Event Generator ◽  
Tetraquark State ◽  
Cross Section Measurement ◽  
Section Measurement

AbstractA method for modelling the prompt production of molecular states using the hadronic rescattering framework of the general-purpose Pythia event generator is introduced. Production cross sections of possible exotic hadronic molecules via hadronic rescattering at the LHC are calculated for the $$\chi _{c1}(3872)$$ χ c 1 ( 3872 ) resonance, a possible tetraquark state, as well as three possible pentaquark states, $$P_c^+(4312)$$ P c + ( 4312 ) , $$P_c^+(4440)$$ P c + ( 4440 ) , and $$P_c^+(4457)$$ P c + ( 4457 ) . For the $$P_c^+$$ P c + states, the expected cross section from $$\Lambda _b$$ Λ b decays is compared to the hadronic-rescattering production. The $$\chi _{c1}(3872)$$ χ c 1 ( 3872 ) cross section is compared to the fiducial $$\chi _{c1}(3872)$$ χ c 1 ( 3872 ) cross-section measurement by LHCb and found to contribute at a level of $${\mathcal {O}({1\%})}$$ O ( 1 % ) . Finally, the expected yields of $$\mathrm {P_c^{+}}$$ P c + production from hadronic rescattering during Run 3 of LHCb are estimated. The prompt background is found to be significantly larger than the prompt $$\mathrm {P_c^{+}}$$ P c + signal from hadronic rescattering.

scholarly journals Evaluated displacement and gas production cross-sections for materials irradiated with intermediate energy nucleons

2017 ◽  
Vol 146 ◽  
pp. 02018 ◽  
Author(s):  
Alexander Yu. Konobeyev ◽  
Ulrich Fischer ◽  
Pavel E. Pereslavtsev ◽  
Stanislav P. Simakov ◽  
Sibel Akça
Keyword(s):  
Cross Sections ◽  
Production Cross ◽  
Intermediate Energy ◽  
Gas Production

scholarly journals The 240Pu(n,f) cross section measurement at the new experimental area at CERN's n_TOF facility

2019 ◽  
Vol 24 ◽  
pp. 139
Author(s):  
A. Stamatopoulos ◽  
For the NTOF Collaboration
Keyword(s):  
Cross Section ◽  
Cross Sections ◽  
Fuel Cycle ◽  
Evaluation Process ◽  
Nuclear Fission ◽  
Nuclear Model ◽  
Model Parameters ◽  
Experimental Area ◽  
Wide Range ◽  
Nuclear Systems

The accurate knowledge of the neutron-induced fission cross-sections of actinides and other isotopes involved in the nuclear fuel cycle are essential for the design of advanced nuclear systems. These experimental data can also provide feedback for the adjustment of nuclear model parameters used in the evaluation process, resulting in further developments of nuclear fission models. In the present work, the 240Pu(n,f) cross-section was measured at CERN's n_TOF facility over a wide range of neutron energies, from a few meV to several MeV, using the time-of-flight technique and a set-up based on MicroMegas detectors. This measurement was the first experiment to be performed in n_TOF's new experimental area (EAR-2), which offers a significantly higher neutron flux compared to the existing experimental area. Preliminary results as well as the experimental procedure, including a brief description of the facility, the sample mounting, the read-out process and the data handling and analysis, are presented.

scholarly journals Status of JENDL

2020 ◽  
Vol 239 ◽  
pp. 09002
Author(s):  
Osamu Iwamoto ◽  
Nobuyuki Iwamoto ◽  
Keiichi Shibata ◽  
Akira Ichihara ◽  
Satoshi Kunieda ◽  
...  
Keyword(s):  
Cross Sections ◽  
Production Cross ◽  
Fission Products ◽  
Nuclear Data ◽  
Data File ◽  
General Purpose ◽  
Reaction Cross ◽  
Activation Cross Section ◽  
Wide Range ◽  
Test Version

Recent progress and future plan of the JENDL project are summarized. Two special purpose files were released recently. One is Photo-nuclear Data File 2016 (JENDL/PD-2016) which contains the data of photo-nuclear reaction cross sections covering a wide area of the nuclear chart. The other one is the JENDL Activation Cross Section File for Nuclear Decommissioning 2017 (JENDL/AD-2017) which provides production cross sections of radioactive nuclei by neutrons. A special purpose file JENDL/ImPACT-2018 dedicated to transmutation of long-lived fission products will be released in 2019. Regarding the general-purpose file, we are preparing to release the next version, which would be made available by 2022 as JENDL-5. Evaluation efforts on nuclides across wide range of nuclei form light to heavy have being made. The first test version JENDL-5α1 was created in 2018. The evaluated data will be updated on the basis of benchmark tests on reactor criticalities and neutron shieldings.

scholarly journals Comprehensive stochastic sensitivities to resonance parameters

2020 ◽  
Vol 239 ◽  
pp. 13008
Author(s):  
Pierre TAMAGNO ◽  
Elias VANDERMEERSCH
Keyword(s):  
Angular Distribution ◽  
Cross Section ◽  
Cross Sections ◽  
Evaluation Process ◽  
Nuclear Model ◽  
Model Parameters ◽  
Probability Method ◽  
Matrix Formalism ◽  
Resonance Parameters ◽  
Critical Configurations

Integral experiments in reactors or critical configurations claim to have very small experimental and technological uncertainties. Therefore these latter can be considered valuable experimental information in nuclear data evaluation. Because in the evaluation process the information is carried by model parameters, to perform a rigorous feedback on a nuclear model parameters p - for instance using a measured reactivity ρ-sensitivities S =∂ρ/ρ⁄∂p/p are needed. In usual integral feedbacks, sensitivity to multi-group cross sections are first obtained with deterministic code using perturbation theory. Then these multi-group cross section sensitivities are “convoluted” with parameter sensitivities in order to provide the sensitivity on nuclear model parameter. Recently stochastic approaches have been elaborated in order to obtain continuous cross-section sensitivities thus avoiding the multi-group discretization. In the present work we used the recent Iterated Fission Probability method of the TRIPOLI4 code [1] in order to obtain directly the sensitivity to nuclear physics parameters. We focus here on the sensitivity on resonance parameters and exemplified the method on the computation of sensitivities for 239Pu and 16O resonance parameters one the ICSBEP benchmark PST001. The underlying nuclear model describing resonant cross sections are based in the R-matrix formalism [2] that provides not only the interaction cross sections but also the angular distribution of the scattered neutrons i.e. differential cross sections. The method has thus been updated in order to compute parameter sensitives that include both contributions: cross section and angular distributions. This extension of the method was tested with exact perturbation of angular distribution and fission spectrum.

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