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LSC measurements of the half-life of 40K
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Uncertainties and Covariances of the Fission Cross Sections and the Fission Neutron Multiplicities for Actinides
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CIELO Collaboration Summary Results: International Evaluations of Neutron Reactions on Uranium, Plutonium, Iron, Oxygen and Hydrogen
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February 2018 |
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Uncertainties of mass extrapolations in Hartree-Fock-Bogoliubov mass models
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May 2014 |
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Measurement of the number of neutrons per fission for 252Cf
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Prompt neutrons from fission
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October 1963 |
The use of the normalized residual in averaging experimental data and in treating outliers
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Nuclear Instruments and Methods in Physics Research Section A: Accelerators, Spectrometers, Detectors and Associated Equipment, Vol. 313, Issue 1-2
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March 1992 |
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On the use of the covariance matrix to fit correlated data
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July 1994 |
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Measurements of prompt and variance for the spontaneous fission of 252Cf and 242Pu
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A least-squares fit of thermal data for fissile nuclei
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January 1984 |
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Resonant neutron capture in 40Ca
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Odd-even effects in radiative neutron capture by 42Ca, 43Ca and 44Ca
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Prompt fission neutron energy spectra induced by fast neutrons
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August 1995 |
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An ENDF-6 compatible evaluation for neutron induced reactions of 232Th in the unresolved resonance region
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July 2008 |
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LSC measurements of the half-life of 40K
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February 2004 |
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Results of an international comparison for the activity measurement of 177Lu
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Procedure for statistical analysis of one-parameter discrepant experimental data
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Needs and Issues of Covariance Data Application
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An Investigation of the Performance of the Unified Monte Carlo Method of Neutron Cross Section Data Evaluation
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Uncertainties and Covariances of the Fission Cross Sections and the Fission Neutron Multiplicities for Actinides
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International Evaluation of Neutron Cross Section Standards
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ENDF/B-VII.1 Nuclear Data for Science and Technology: Cross Sections, Covariances, Fission Product Yields and Decay Data
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Experimental Nuclear Reaction Data Uncertainties: Basic Concepts and Documentation
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Determination of Resonance Parameters and their Covariances from Neutron Induced Reaction Cross Section Data
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December 2012 |
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Towards a More Complete and Accurate Experimental Nuclear Reaction Data Library (EXFOR): International Collaboration Between Nuclear Reaction Data Centres (NRDC)
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June 2014 |
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Nuclear Data Uncertainty Quantification: Past, Present and Future
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January 2015 |
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Uncertainty-driven nuclear data evaluation including thermal (n, α ) applied to 59 Ni
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November 2017 |
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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
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Evaluation of the Neutron Data Standards
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February 2018 |
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February 2018 |
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IAEA CIELO Evaluation of Neutron-induced Reactions on 235 U and 238 U Targets
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February 2018 |
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Reference Cross Sections for Charged-particle Monitor Reactions
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February 2018 |
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TENDL: Complete Nuclear Data Library for Innovative Nuclear Science and Technology
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January 2019 |
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Applying a Template of Expected Uncertainties to Updating 239Pu(n,f) Cross-section Covariances in the Neutron Data Standards Database
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January 2020 |
The cross-section of the 10B(n,α)7Li reaction measured in the MeV energy range
- Giorginis, Georgios; Khryachkov, Vitali
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Nuclear Instruments and Methods in Physics Research Section A: Accelerators, Spectrometers, Detectors and Associated Equipment, Vol. 562, Issue 2
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June 2006 |
The use of C6D6 detectors for neutron induced capture cross-section measurements in the resonance region
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Nuclear Instruments and Methods in Physics Research Section A: Accelerators, Spectrometers, Detectors and Associated Equipment, Vol. 577, Issue 3
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Impact of model defect and experimental uncertainties on evaluated output
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Nuclear Instruments and Methods in Physics Research Section A: Accelerators, Spectrometers, Detectors and Associated Equipment, Vol. 723
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Nuclear data evaluation methodology including estimates of covariances
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New fit of thermal neutron constants (TNC) for 233,235 U, 239,241 Pu and 252 Cf(sf): Microscopic vs. maxwellian data
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Experiments in the EXFOR library for evaluation of thermal neutron constants
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Template for estimating uncertainties of measured neutron-induced fission cross-sections
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January 2018 |
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Neutron-Induced Fission of 233 U, 238 U, 232 Th, 239 Pu, 237 Np, nat Pb and 209 Bi Relative to 235 U in the Energy Range 1-200 MeV
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August 2002 |
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Neutron Yield from the Spontaneous Fission of 252 Cf (bar nu)
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January 1985 |
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Statistical determination of a comparison reference value using hidden errors
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Outlier rejection for the weighted-mean KCRV
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The uncertainty associated with the weighted mean of measurement data
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February 2006 |
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The generalized weighted mean of correlated quantities
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August 2006 |
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Weighted means statistics in interlaboratory studies
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May 2009 |
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Uncertainties in gamma-ray spectrometry
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May 2015 |
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Uncertainty of combined activity estimations
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May 2015 |
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An outlier-resistant indicator of anomalies among inter-laboratory comparison data with associated uncertainty
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November 2018 |
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Neutron Yield of Cf 252 Based on Absolute Measurements of the Neutron Rate and Fission Rate
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New Maxwellian averaged neutron capture cross sections for 3 5 , 3 7 Cl
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Neutron capture cross section of Th 232 measured at the n_TOF facility at CERN in the unresolved resonance region up to 1 MeV
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May 2006 |
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Determination of the stellar ( n , γ ) cross section of Ca 40 with accelerator mass spectrometry
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June 2009 |
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Astrophysical reaction rates for Ni 58 , 60 ( n , γ ) from new neutron capture cross section measurements
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November 2010 |
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Experimental neutron capture data of 58 Ni from the CERN n_TOF facility
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January 2014 |
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Uncertainties of mass extrapolations in Hartree-Fock-Bogoliubov mass models
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May 2014 |
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High-accuracy determination of the U 238 / U 235 fission cross section ratio up to ≈ 1 GeV at n_TOF at CERN
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February 2015 |
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Measurement of the stellar Ni 58 ( n , γ ) Ni 59 cross section with accelerator mass spectrometry
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March 2017 |
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Precise measurement of the thermal and stellar Fe 54 ( n , γ ) Fe 55 cross sections via accelerator mass spectrometry
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August 2017 |
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Review of Particle Physics
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August 2018 |
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Neutron capture cross section measurements for 197Au from 3.5 to 84 keV at GELINA
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August 2014 |
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Bayesian Monte Carlo method for nuclear data evaluation
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December 2015 |
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Neutron Capture Cross Section of 232 Th
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February 2001 |
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Differential Cross-Section Measurement for the 10 B( n , α ) 7 Li Reaction
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October 2002 |
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Evaluation of Data with Systematic Errors
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November 2003 |
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Determination of the 232 Th( n , γ) Cross Section from 4 to 140 keV at GELINA
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January 2006 |
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Peelle’s Pertinent Puzzle: A Fake Due to Improper Analysis
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Evaluation and Uncertainty Quantification of Prompt Fission Neutron Spectra of Uranium and Plutonium Isotopes
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September 2013 |
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Fast Neutron–Induced Fission Cross Sections of 233, 234, 236, 238 U up to 200 MeV
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September 2014 |
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An Absolute Measurement of v̄ of Cf 252
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May 1963 |
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Measurements of the Neutron-Induced Fission Cross Sections of 234 U, 236 U, and 238 U Relative to 235 U from 0.1 to 30 MeV
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July 1977 |
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Measurement of the Uranium-238 to Uranium-235 Fission Cross-Section Ratio for Neutron Energies Between 0.1 and 25 MeV
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October 1978 |
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A Measurement of the Average Number of Prompt Neutrons from Spontaneous Fission of Californium-252
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April 1982 |
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A New Formulation of the Unified Monte Carlo Approach (UMC-B) and Cross-Section Evaluation for the Dosimetry Reaction 55 Mn(n,γ) 56 Mn
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March 2012 |
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Sur la représentation approchée d'une fonction par des fractions rationnelles
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January 1892 |
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Evaluation of the Covariance Matrix of 239Pu Neutronic Cross Sections in the Continuum Using the Backward-Forward Monte-Carlo Method
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August 2011 |