Evaluation of the Neutron Data Standards

Carlson, A. D.; Pronyaev, V. G.; Capote, R.; Hale, G. M.; Chen, Z. -P.; Duran, I.; Hambsch, F. -J.; Kunieda, S.; Mannhart, W.; Marcinkevicius, B.; Nelson, R. O.; Neudecker, D.; Noguere, G.; Paris, M.; Simakov, S. P.; Schillebeeckx, P.; Smith, D. L.; Tao, X.; Trkov, A.; Wallner, A.; Wang, W.

doi:10.1016/j.nds.2018.02.002

Title: Evaluation of the Neutron Data Standards

Abstract

With the need for improving existing nuclear data evaluations, (e.g., ENDF/B-VIII.0 and JEFF-3.3 releases) the first step was to evaluate the standards for use in such a library. This new standards evaluation made use of improved experimental data and some developments in the methodology of analysis and evaluation. In addition to the work on the traditional standards, this work produced the extension of some energy ranges and includes new reactions that are called reference cross sections. Since the effort extends beyond the traditional standards, it is called the neutron data standards evaluation. This international effort has produced new evaluations of the following cross section standards: the H(n,n), ⁶Li(n,t), ¹⁰B(n,α), ¹⁰B(n,α₁γ), ^natC(n,n), Au(n,γ), ²³⁵U(n,f) and ²³⁸U(n,f). Also in the evaluation process the ²³⁸U(n,γ) and ²³⁹Pu(n,f) cross sections that are not standards were evaluated. Evaluations were also obtained for data that are not traditional standards: the Maxwellian spectrum averaged cross section for the Au(n,γ) cross section at 30 keV; reference cross sections for prompt γ-ray production in fast neutron-induced reactions; reference cross sections for very high energy fission cross sections; the ²⁵²Cf spontaneous fission neutron spectrum and the ²³⁵U prompt fission neutron spectrum induced by thermal incident neutrons; and the thermal neutronmore »« less

Authors:

Carlson, A. D. ^[1]; Pronyaev, V. G. ^[2]; Capote, R. ^[3]; Hale, G. M. ^[4]; Chen, Z. -P. ^[5]; Duran, I. ^[6]; Hambsch, F. -J. ^[7]; Kunieda, S. ^[8]; Mannhart, W. ^[9]; Marcinkevicius, B. ^[10]; Nelson, R. O. ^[4]; Neudecker, D. ^[4]; Noguere, G. ^[11]; Paris, M. ^[4]; Simakov, S. P. ^[12]; Schillebeeckx, P. ^[7]; Smith, D. L. ^[13]; Tao, X. ^[14]; Trkov, A. ^[3]; Wallner, A. ^[15] more »

National Inst. of Standards and Technology (NIST), Gaithersburg, MD (United States)
State Corporation Rosatom, Moscow (Russia)
International Atomic Energy Agency, Vienna (Austria)
Los Alamos National Lab. (LANL), Los Alamos, NM (United States)
Tsinghua Univ., Beijing (China)
Univ. de Santiago de Compostela (Spain)
EC-JRC-Directorate G, Geel (Belgium)
Japan Atomic Energy Agency, Ibaraki (Japan)
Physikalisch-Technische Bundesanstalt, Braunschweig (Germany)
International Atomic Energy Agency, Vienna (Austria) ; Uppsala Univ. (Sweden)
Alternative Energies and Atomic Energy Commission (CEA), Cadarache (France)
Karlsruhe Inst. of Technology (KIT), Eggenstein-Leopoldshafen (Germany)
Argonne National Lab. (ANL), Argonne, IL (United States)
China Inst. of Atomic Energy, Beijing (China)
Univ. of Vienna (Austria); Australian National Univ., Canberra, ACT (Australia)

Publication Date:: Wed Mar 07 00:00:00 EST 2018

Research Org.:: National Inst. of Standards and Technology (NIST), Boulder, CO (United States); Los Alamos National Laboratory (LANL), Los Alamos, NM (United States)

Sponsoring Org.:: USDOE Office of Science (SC), Nuclear Physics (NP)

OSTI Identifier:: 1615951

Alternate Identifier(s):: OSTI ID: 1427382

Report Number(s):: LA-UR-17-30674
Journal ID: ISSN 0090-3752; TRN: US2106391

Grant/Contract Number:: SC0011527; AC52-06NA25396

Resource Type:: Accepted Manuscript

Journal Name:: Nuclear Data Sheets

Additional Journal Information:: Journal Volume: 148; Journal Issue: C; Journal ID: ISSN 0090-3752

Publisher:: Elsevier

Country of Publication:: United States

Language:: English

Subject:: 73 NUCLEAR PHYSICS AND RADIATION PHYSICS; standards; neutron standards; cross sections; evaluation; ENDF

Citation Formats


                    Carlson, A. D., Pronyaev, V. G., Capote, R., Hale, G. M., Chen, Z. -P., Duran, I., Hambsch, F. -J., Kunieda, S., Mannhart, W., Marcinkevicius, B., Nelson, R. O., Neudecker, D., Noguere, G., Paris, M., Simakov, S. P., Schillebeeckx, P., Smith, D. L., Tao, X., Trkov, A., Wallner, A., and Wang, W. Evaluation of the Neutron Data Standards.  United States: N. p., 2018. 
Web.  doi:10.1016/j.nds.2018.02.002.

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                    Carlson, A. D., Pronyaev, V. G., Capote, R., Hale, G. M., Chen, Z. -P., Duran, I., Hambsch, F. -J., Kunieda, S., Mannhart, W., Marcinkevicius, B., Nelson, R. O., Neudecker, D., Noguere, G., Paris, M., Simakov, S. P., Schillebeeckx, P., Smith, D. L., Tao, X., Trkov, A., Wallner, A., & Wang, W. Evaluation of the Neutron Data Standards.  United States.  https://doi.org/10.1016/j.nds.2018.02.002

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                    Carlson, A. D., Pronyaev, V. G., Capote, R., Hale, G. M., Chen, Z. -P., Duran, I., Hambsch, F. -J., Kunieda, S., Mannhart, W., Marcinkevicius, B., Nelson, R. O., Neudecker, D., Noguere, G., Paris, M., Simakov, S. P., Schillebeeckx, P., Smith, D. L., Tao, X., Trkov, A., Wallner, A., and Wang, W. Wed .  
"Evaluation of the Neutron Data Standards".  United States.  https://doi.org/10.1016/j.nds.2018.02.002.  https://www.osti.gov/servlets/purl/1615951.

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@article{osti_1615951,

  title        = {Evaluation of the Neutron Data Standards},

  author       = {Carlson, A. D. and Pronyaev, V. G. and Capote, R. and Hale, G. M. and Chen, Z. -P. and Duran, I. and Hambsch, F. -J. and Kunieda, S. and Mannhart, W. and Marcinkevicius, B. and Nelson, R. O. and Neudecker, D. and Noguere, G. and Paris, M. and Simakov, S. P. and Schillebeeckx, P. and Smith, D. L. and Tao, X. and Trkov, A. and Wallner, A. and Wang, W.},

  abstractNote = {With the need for improving existing nuclear data evaluations, (e.g., ENDF/B-VIII.0 and JEFF-3.3 releases) the first step was to evaluate the standards for use in such a library. This new standards evaluation made use of improved experimental data and some developments in the methodology of analysis and evaluation. In addition to the work on the traditional standards, this work produced the extension of some energy ranges and includes new reactions that are called reference cross sections. Since the effort extends beyond the traditional standards, it is called the neutron data standards evaluation. This international effort has produced new evaluations of the following cross section standards: the H(n,n), 6Li(n,t), 10B(n,α), 10B(n,α1γ), natC(n,n), Au(n,γ), 235U(n,f) and 238U(n,f). Also in the evaluation process the 238U(n,γ) and 239Pu(n,f) cross sections that are not standards were evaluated. Evaluations were also obtained for data that are not traditional standards: the Maxwellian spectrum averaged cross section for the Au(n,γ) cross section at 30 keV; reference cross sections for prompt γ-ray production in fast neutron-induced reactions; reference cross sections for very high energy fission cross sections; the 252Cf spontaneous fission neutron spectrum and the 235U prompt fission neutron spectrum induced by thermal incident neutrons; and the thermal neutron constants. The data and covariance matrices of the uncertainties were obtained directly from the evaluation procedure.},

  doi          = {10.1016/j.nds.2018.02.002},

  journal      = {Nuclear Data Sheets},

  number       = C,

  volume       = 148,

  place        = {United States},

  year         = {Wed Mar 07 00:00:00 EST 2018},

  month        = {Wed Mar 07 00:00:00 EST 2018}

}

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Works referencing / citing this record:

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Measurement of the U 235 ( n , f ) prompt fission neutron spectrum from 10 keV to 10 MeV induced by neutrons of energy from 1 MeV to 20 MeV

Journal Article Kelly, Keegan John ; Gomez, Jaime A. ; Devlin, Matthew James ; ... - Physical Review. C

The characterization of fission-driven nuclear systems primarily relies on calculations of neutron-induced chain reactions, and these calculations require evaluated nuclear data as input. Calculation accuracy heavily depends on input nuclear data evaluation accuracy, and thus high precision on the experimental input to the nuclear data evaluation is essential for fundamental quantities like the energy spectrum of neutrons emitted from neutron-induced fission (i.e., the prompt fission neutron spectrum, PFNS). Despite decades of measurement efforts, prior to the measurements described in this work there were only three literature data sets for the ²³⁵U(n,f) PFNS at incident neutron energies above 1.0 MeV considered reliable for inclusion in nuclear data evaluations and no reliable data sets above 3.0 MeV incident neutron energy. In this work we report on new measurements of the ²³⁵U(n,f) PFNS spanning a grid of 1.0–20.0 MeV in incident neutron energy and 0.01–10.0 MeV in outgoing (PFNS) neutron energy. These measurements were carried out at the Weapons Neutron Research facility at the Los Alamos Neutron Science Center and used a multifoil parallel-plate avalanche counter target with both a Li-glass and a liquid scintillator detector array in separate experiments to span the quoted outgoing neutron energy ranges. The PFNS results are shown in terms of the energy spectra themselves as well as the average PFNS energymore »« less
https://doi.org/10.1103/physrevc.105.044615

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Covariances Obtained from an Evaluation of the Neutron Cross Section Standards

Journal Article Carlson, A.D. ; Badikov, S A ; Chen, Zhenpeng ; ... - Nuclear Data Sheets

New measurements and an improved evaluation process were used to obtain a new evaluation of the neutron cross section standards. Efforts were made to include as much information as possible on the components of the data uncertainties that were then used to obtain the covariance matrices for the experimental data. Evaluations were produced from this process for the {sup 6}Li(n,t), {sup 10}B(n,{alpha}), {sup 10}B(n,{alpha}{sub 1}{gamma}), {sup 197}Au(n,{gamma}), {sup 235}U(n,f), and {sup 238}U(n,f) standard cross sections as well as the non-standard {sup 6}Li(n,n), {sup 10}B(n,n), {sup 238}U(n,{gamma}) and {sup 239}Pu(n,f) cross sections. There is a general increase in the cross sectionsmore »« less
https://doi.org/10.1016/j.nds.2008.11.019
Validating the ENDF-B/VII{sup 235}U(n{sub th},f) prompt fission neutron spectrum using updated dosimetry cross sections (IRDFF)

Conference Capote, R. ; Zolotarev, K. I. ; Pronyaev, V. G. ; ...

The International Reactor Dosimetry File IRDF-2002 released in 2004 by the IAEA contains cross-section data and corresponding uncertainties for 66 dosimetry reactions. New cross-section evaluations have become available recently that re-define some of these dosimetry reactions for reactor applications including: 1) high fidelity evaluation work undertaken by one of the authors (KIZ); 2) evaluations from the ENDF/B-VII libraries that cover reactions within the International Evaluation of Neutron Cross-Section Standards; and 3) evaluations from JENDL-3.1 and JENDL-4 libraries. Overall, 37 new evaluations of dosimetry reactions have been assessed to determine whether they should be adopted to update and improve IRDF-2002. Amore »« less

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Title: Evaluation of the Neutron Data Standards

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Measurement of the 238U Radiative Capture Cross Section with C6D6 at the CERN n_TOF Facility journal, May 2014

PINO—a tool for simulating neutron spectra resulting from the 7Li(p,n) reaction journal, September 2009

Measurement of the absolute differential cross section for np elastic scattering at 194 MeV journal, October 2006

High-precision Measurement of the 238U(n,γ) Cross Section with the Total Absorption Calorimeter (TAC) at n_TOF, CERN journal, May 2014

Neutron-induced fission cross section of nat Pb and Bi 209 from threshold to 1 GeV: An improved parametrization journal, April 2011

Neutron capture cross section measurements for 238U in the resonance region at GELINA journal, June 2016

Novel Method to Study Neutron Capture of U 235 and U 238 Simultaneously at keV Energies journal, May 2014

Cross Sections for 239 Pu( n , f ) and 241 Pu( n , f ) in the Range E n = 0.01 eV to 200 MeV journal, June 2010

CONRAD Evaluation Code: Development Status and Perspectives journal, April 2014

Definition of a standard neutron field with the 7 Li( p , n ) 7 Be reaction journal, May 2012

Gold Neutron Capture Cross Section from 100 to 2000 keV journal, November 1981

International Evaluation of Neutron Cross Section Standards journal, December 2009

Measurement of 89Y(n,2n) spectral averaged cross section in LR-0 special core reactor spectrum journal, December 2017

ENDF/B-VII.0: Next Generation Evaluated Nuclear Data Library for Nuclear Science and Technology journal, December 2006

Charged-particle spectrometry using a pencil-beam DT neutron source for double-differential cross-section measurement journal, December 2006

Neutron capture cross section measurements for 197Au from 3.5 to 84 keV at GELINA journal, August 2014

Neutron inelastic scattering measurements on the stable isotopes of titanium journal, July 2017

Quasi-stellar neutrons from the 7 Li( p , n ) 7 Be reaction with an energy-broadened proton beam journal, May 2012

Prompt Fission Neutron Spectra of Actinides journal, January 2016

Au 197 ( n , γ ) cross section in the resonance region journal, April 2010

Data Covariances from R-Matrix Analyses of Light Nuclei journal, January 2015

Fast Neutron–Induced Fission Cross Sections of 233, 234, 236, 238 U up to 200 MeV journal, September 2014

Uncertainties and Covariances of the Fission Cross Sections and the Fission Neutron Multiplicities for Actinides journal, December 2008

Energy spectra of X-ray clusters of galaxies journal, November 1976

ENDF/B-VIII.0: The 8 th Major Release of the Nuclear Reaction Data Library with CIELO-project Cross Sections, New Standards and Thermal Scattering Data journal, February 2018

10B and 6Li Nuclear Data Measurements for Incident Neutron Energies up to 3 MeV journal, May 2014

Cross section and γ -ray spectra for U 238 ( n , γ ) measured with the DANCE detector array at the Los Alamos Neutron Science Center journal, March 2014

Towards a More Complete and Accurate Experimental Nuclear Reaction Data Library (EXFOR): International Collaboration Between Nuclear Reaction Data Centres (NRDC) journal, June 2014

Induced nuclear fission accompanied by pion emission journal, August 2001

np scattering measurements at 162 MeV and the π NN coupling constant journal, March 1998

Measurement of differential and angle-integrated cross sections of the 6Li(n,t)4He reaction in the MeV neutron energy range journal, October 2006

Determination of the 232 Th( n , γ) Cross Section from 4 to 140 keV at GELINA journal, January 2006

Updating and Extending the IRDF-2002 Dosimetry Library journal, April 2012

The 235 U( n , f ) Prompt Fission Neutron Spectrum at 100 K Input Neutron Energy journal, May 2010

The effect of particle leaking and its implications for measurements of the (n,α) reaction on light elements by using ionisation chambers journal, February 2005

Excitation function shape and neutron spectrum of the Li 7 ( p , n ) Be 7 reaction near threshold journal, September 2016

Au 197 ( n , γ ) cross section in the unresolved resonance region journal, March 2011

ENDF/B-VII.1 Nuclear Data for Science and Technology: Cross Sections, Covariances, Fission Product Yields and Decay Data journal, December 2011

Particle-unstable and weakly-bound light nuclei with a Sturmian approach that preserves the Pauli principle journal, June 2007

Measurement of the 477.6-keV γ -ray production cross section following inelastic neutron scattering by Li 7 journal, February 2016

Gold neutron-capture cross section from 3 to 550 keV journal, April 1975

Neutron capture cross section of Au 197 : A standard for stellar nucleosynthesis journal, February 1988

Gamma-Ray Production Cross Sections in Multiple Channels for Neutron-Induced Reaction on 48 Ti for E n = 1 to 200 MeV journal, September 2007

Evaluation of the Prompt Fission Neutron Spectrum of Thermal-neutron Induced Fission in U-235 journal, January 2015

On the search for a (n,f) cross-section reference at intermediate energies journal, January 2017

THE MEASUREMENTS OF THE DIFFERENTIAL ELASTIC NEUTRON CROSS-SECTIONS OF CARBON FOR ENERGIES FROM 2 TO 133 keV conference, January 2012

Cross-section measurement for the 10B(n, α)7Li reaction at 4.0 and 5.0MeV journal, October 2008

Measurements of the neutron-proton and neutron-carbon total cross section from 150 to 800 keV journal, January 2013

MCNP6 Fission Cross Section Calculations at Intermediate and High Energies journal, April 2014

n+12C Cross Sections from an R-matrix Analysis of Reactions in the 13C System journal, April 2014

Current Issues in Nuclear Data Evaluation Methodology: 235U Prompt Fission Neutron Spectra and Multiplicity for Thermal Neutrons journal, January 2015

Investigation of the prompt neutron emission mechanism in low energy fission of 235,233 U(n th , f) and 252 Cf(sf) journal, January 2010

Anomalous neutron Compton scattering from molecular hydrogen journal, August 2005

Measurement of the 235U(n, f) cross section relative to the 6Li(n, t) and 10B(n,$ \alpha$) standards from thermal to 170 keV neutron energy range at n_TOF journal, July 2019

Review of nuclear data for naturally occurring radionuclides applied to environmental applications journal, February 2019

Correlation $\overline{\nu}_{p} - \sigma$ for U-Pu in the thermal and resonance neutron range via integral information journal, September 2019

Measurement of the $^{235}$U(n, f) cross section relative to the $^{6}$Li(n, t) and $^{10}$B(n, α) standards from thermal to 170 keV neutron energy range at n_TOF text, January 2019

Conception and Software Implementation of a Nuclear Data Evaluation Pipeline journal, March 2021

1H(n,el) as a Cross Section Reference in a White Source Neutron Beam With the fissionTPC preprint, January 2019

Measurement of the 238U Radiative Capture Cross Section with C6D6 at the CERN n_TOF Facility
journal, May 2014

PINO—a tool for simulating neutron spectra resulting from the 7Li(p,n) reaction
journal, September 2009

Measurement of the absolute differential cross section for $np$ elastic scattering at 194 MeV
journal, October 2006

High-precision Measurement of the 238U(n,γ) Cross Section with the Total Absorption Calorimeter (TAC) at n_TOF, CERN
journal, May 2014

Neutron-induced fission cross section of $^{nat}$ Pb and ${}^{209}{Bi}$ from threshold to 1 GeV: An improved parametrization
journal, April 2011

Neutron capture cross section measurements for 238U in the resonance region at GELINA
journal, June 2016

Novel Method to Study Neutron Capture of ${}^{235}U$ and ${}^{238}U$ Simultaneously at keV Energies
journal, May 2014

Cross Sections for ²³⁹ Pu( n , f ) and ²⁴¹ Pu( n , f ) in the Range E _n = 0.01 eV to 200 MeV
journal, June 2010

CONRAD Evaluation Code: Development Status and Perspectives
journal, April 2014

Definition of a standard neutron field with the $^{7}$ Li( $p, n$ ) $^{7}$ Be reaction
journal, May 2012

Gold Neutron Capture Cross Section from 100 to 2000 keV
journal, November 1981

International Evaluation of Neutron Cross Section Standards
journal, December 2009

Measurement of 89Y(n,2n) spectral averaged cross section in LR-0 special core reactor spectrum
journal, December 2017

ENDF/B-VII.0: Next Generation Evaluated Nuclear Data Library for Nuclear Science and Technology
journal, December 2006

Charged-particle spectrometry using a pencil-beam DT neutron source for double-differential cross-section measurement
journal, December 2006

Neutron capture cross section measurements for 197Au from 3.5 to 84 keV at GELINA
journal, August 2014

Neutron inelastic scattering measurements on the stable isotopes of titanium
journal, July 2017

Quasi-stellar neutrons from the $^{7}$ Li( $p, n$ ) $^{7}$ Be reaction with an energy-broadened proton beam
journal, May 2012

Prompt Fission Neutron Spectra of Actinides
journal, January 2016

${}^{197}{Au}$ ( $n, γ$ ) cross section in the resonance region
journal, April 2010

Data Covariances from R-Matrix Analyses of Light Nuclei
journal, January 2015

Fast Neutron–Induced Fission Cross Sections of ^{233, 234, 236, 238} U up to 200 MeV
journal, September 2014

Uncertainties and Covariances of the Fission Cross Sections and the Fission Neutron Multiplicities for Actinides
journal, December 2008

Energy spectra of X-ray clusters of galaxies
journal, November 1976

ENDF/B-VIII.0: The 8 th Major Release of the Nuclear Reaction Data Library with CIELO-project Cross Sections, New Standards and Thermal Scattering Data
journal, February 2018

10B and 6Li Nuclear Data Measurements for Incident Neutron Energies up to 3 MeV
journal, May 2014

Cross section and $γ$ -ray spectra for ${}^{238}U$ ( $n$ , $γ$ ) measured with the DANCE detector array at the Los Alamos Neutron Science Center
journal, March 2014

Towards a More Complete and Accurate Experimental Nuclear Reaction Data Library (EXFOR): International Collaboration Between Nuclear Reaction Data Centres (NRDC)
journal, June 2014

Induced nuclear fission accompanied by pion emission
journal, August 2001

$np$ scattering measurements at 162 MeV and the $π NN$ coupling constant
journal, March 1998

Measurement of differential and angle-integrated cross sections of the 6Li(n,t)4He reaction in the MeV neutron energy range
journal, October 2006

Determination of the ²³² Th( n , γ) Cross Section from 4 to 140 keV at GELINA
journal, January 2006

Updating and Extending the IRDF-2002 Dosimetry Library
journal, April 2012

The ²³⁵ U( n , f ) Prompt Fission Neutron Spectrum at 100 K Input Neutron Energy
journal, May 2010

The effect of particle leaking and its implications for measurements of the (n,α) reaction on light elements by using ionisation chambers
journal, February 2005

Excitation function shape and neutron spectrum of the ${}^{7}{Li} (p, n) {}^{7}{Be}$ reaction near threshold
journal, September 2016

${}^{197}{Au}$ ( $n, γ$ ) cross section in the unresolved resonance region
journal, March 2011

ENDF/B-VII.1 Nuclear Data for Science and Technology: Cross Sections, Covariances, Fission Product Yields and Decay Data
journal, December 2011

Particle-unstable and weakly-bound light nuclei with a Sturmian approach that preserves the Pauli principle
journal, June 2007

Measurement of the 477.6-keV $γ$ -ray production cross section following inelastic neutron scattering by ${}^{7}{Li}$
journal, February 2016

Gold neutron-capture cross section from 3 to 550 keV
journal, April 1975

Neutron capture cross section of ${}^{197}{Au}$ : A standard for stellar nucleosynthesis
journal, February 1988

Gamma-Ray Production Cross Sections in Multiple Channels for Neutron-Induced Reaction on ⁴⁸ Ti for E _n = 1 to 200 MeV
journal, September 2007

Evaluation of the Prompt Fission Neutron Spectrum of Thermal-neutron Induced Fission in U-235
journal, January 2015

On the search for a (n,f) cross-section reference at intermediate energies
journal, January 2017

THE MEASUREMENTS OF THE DIFFERENTIAL ELASTIC NEUTRON CROSS-SECTIONS OF CARBON FOR ENERGIES FROM 2 TO 133 keV
conference, January 2012

Cross-section measurement for the 10B(n, α)7Li reaction at 4.0 and 5.0MeV
journal, October 2008

Measurements of the neutron-proton and neutron-carbon total cross section from 150 to 800 keV
journal, January 2013

MCNP6 Fission Cross Section Calculations at Intermediate and High Energies
journal, April 2014

n+12C Cross Sections from an R-matrix Analysis of Reactions in the 13C System
journal, April 2014

Current Issues in Nuclear Data Evaluation Methodology: 235U Prompt Fission Neutron Spectra and Multiplicity for Thermal Neutrons
journal, January 2015

Investigation of the prompt neutron emission mechanism in low energy fission of ^235,233 U(n _th , f) and ²⁵² Cf(sf)
journal, January 2010

Anomalous neutron Compton scattering from molecular hydrogen
journal, August 2005

Measurement of the 235U(n, f) cross section relative to the 6Li(n, t) and 10B(n,$ \alpha$) standards from thermal to 170 keV neutron energy range at n_TOF
journal, July 2019

Review of nuclear data for naturally occurring radionuclides applied to environmental applications
journal, February 2019

Correlation $\overline{\nu}_{p} - \sigma$ for U-Pu in the thermal and resonance neutron range via integral information
journal, September 2019

Measurement of the $^{235}$U(n, f) cross section relative to the $^{6}$Li(n, t) and $^{10}$B(n, α) standards from thermal to 170 keV neutron energy range at n_TOF
text, January 2019

Conception and Software Implementation of a Nuclear Data Evaluation Pipeline
journal, March 2021

1H(n,el) as a Cross Section Reference in a White Source Neutron Beam With the fissionTPC
preprint, January 2019