Sigma Web Interface for Reactor Data Applications

Pritychenko, B.; Sonzogni, A. A.

doi:10.2172/970612

Cited by 19 publications

(24 citation statements)

References 15 publications

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“…NeuNeutron Thermal Cross ... [47,48] at T=0 and 300 • K. An extensive analysis of the ENDF astrophysical data has been performed in our previous work [5]. In this work, we will extend the analysis to neutron thermal cross sections, Westcott factors and resonance integrals.…”

Section: Resultsmentioning

confidence: 99%

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Neutron Thermal Cross Sections, Westcott Factors, Resonance Integrals, Maxwellian Averaged Cross Sections and Astrophysical Reaction Rates Calculated from the ENDF/B-VII.1, JEFF-3.1.2, JENDL-4.0, ROSFOND-2010, CENDL-3.1 and EAF-2010 Evaluated Data Libraries

Pritychenko

Mughabghab

2012

Nuclear Data Sheets

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We present calculations of neutron thermal cross sections, Westcott factors, resonance integrals, Maxwellianaveraged cross sections and astrophysical reaction rates for 843 ENDF materials using data from the major evaluated nuclear libraries and European activation file. Extensive analysis of newly-evaluated neutron reaction cross sections, neutron covariances, and improvements in data processing techniques motivated us to calculate nuclear industry and neutron physics quantities, produce s-process Maxwellian-averaged cross sections and astrophysical reaction rates, systematically calculate uncertainties, and provide additional insights on currently available neutron-induced reaction data. Nuclear reaction calculations are discussed and new results are presented. Due to space limitations, the present paper contains only calculated Maxwellian-averaged cross sections and their uncertainties. The complete data sets for all results are published in the Brookhaven National Laboratory report.

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Section: Resultsmentioning

confidence: 99%

“…Current work is the most complete calculation of ENDF values up-to-date [4,5,47] and reflects the strong USNDP commitment to the nuclear data research and development. The list of improvements include:…”

Section: G Major Improvements Of Present Work With Previous Evaluationsmentioning

confidence: 99%

Neutron Thermal Cross Sections, Westcott Factors, Resonance Integrals, Maxwellian Averaged Cross Sections and Astrophysical Reaction Rates Calculated from the ENDF/B-VII.1, JEFF-3.1.2, JENDL-4.0, ROSFOND-2010, CENDL-3.1 and EAF-2010 Evaluated Data Libraries

Pritychenko

Mughabghab

2012

Nuclear Data Sheets

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“…The detector was calibrated using a multiple standard γ-ray point source consisting of 57,60 Co, 88 Y, 109 Cd, 113 Sn 137 Cs, 139 Ce and 241 Am radioisotopes. The reaction and decay data used for the γ-ray spectrometry were taken from NuDat 2.7 [3], LiveChart [15] and QCalc [16] (Table 1).…”

Section: Methodsmentioning

confidence: 99%

Activation cross sections of deuteron-induced reactions on niobium up to 24 MeV

Aikawa

Komori

Haba

2018

Nuclear Instruments and Methods in Physics Research Section B:

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“…Lab. (Pritychenko and Sonzogni, 2003), are given in Fig. 2, together with the theoretical predictions.…”

Section: Excitation Functionsmentioning

confidence: 96%

Cross sections of deuteron induced reactions on natSm for production of the therapeutic radionuclide 145Sm and 153Sm

Tárkányi¹,

Hermanne²,

Takács³

et al. 2014

Applied Radiation and Isotopes

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At present, targeted radiotherapy (TR) is acknowledged to have great potential in oncology. A large list of interesting radionuclides is identified, including several radioisotopes of lanthanides, amongst them 145 Sm and 153 Sm. In this work the possibility of their production at a cyclotron was investigated using a deuteron beam and a samarium target. The excitation functions of the nat Sm(d,x) 145,153 Sm reactions were determined for deuteron energies up to 50 MeV using the stacked-foil technique and high-resolution γ-ray spectrometry. The measured cross sections and the contributing reactions were analyzed by comparison with results of the ALICE, EMPIRE and TALYS nuclear reaction codes. A short overview and comparison of possible production routes is given.

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Sigma Web Interface for Reactor Data Applications

Cited by 19 publications

References 15 publications

Neutron Thermal Cross Sections, Westcott Factors, Resonance Integrals, Maxwellian Averaged Cross Sections and Astrophysical Reaction Rates Calculated from the ENDF/B-VII.1, JEFF-3.1.2, JENDL-4.0, ROSFOND-2010, CENDL-3.1 and EAF-2010 Evaluated Data Libraries

Neutron Thermal Cross Sections, Westcott Factors, Resonance Integrals, Maxwellian Averaged Cross Sections and Astrophysical Reaction Rates Calculated from the ENDF/B-VII.1, JEFF-3.1.2, JENDL-4.0, ROSFOND-2010, CENDL-3.1 and EAF-2010 Evaluated Data Libraries

Activation cross sections of deuteron-induced reactions on niobium up to 24 MeV

Cross sections of deuteron induced reactions on natSm for production of the therapeutic radionuclide 145Sm and 153Sm

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Sigma Web Interface for Reactor Data Applications

Cited by 19 publications

References 15 publications

Neutron Thermal Cross Sections, Westcott Factors, Resonance Integrals, Maxwellian Averaged Cross Sections and Astrophysical Reaction Rates Calculated from the ENDF/B-VII.1, JEFF-3.1.2, JENDL-4.0, ROSFOND-2010, CENDL-3.1 and EAF-2010 Evaluated Data Libraries

Neutron Thermal Cross Sections, Westcott Factors, Resonance Integrals, Maxwellian Averaged Cross Sections and Astrophysical Reaction Rates Calculated from the ENDF/B-VII.1, JEFF-3.1.2, JENDL-4.0, ROSFOND-2010, CENDL-3.1 and EAF-2010 Evaluated Data Libraries

Activation cross sections of deuteron-induced reactions on niobium up to 24 MeV

Cross sections of deuteron induced reactions on natSm for production of the therapeutic radionuclide 145Sm and 153Sm

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Activation cross sections of deuteron-induced reactions on niobium up to 24 MeV