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ENDF/B-VII beta2 Web interface ( | Download Scientific Diagram
ENDF Releases
PPT - NJOY Code Status PowerPoint Presentation, free download - ID:4448378
ENDF/B-V1 Coupled Photon-Electron Data for Use in Radiation Shielding ...
PPT - Nuclear Reaction Physics PowerPoint Presentation, free download ...
Decay Data for Fusion Applications: Status, Issues and Needs - ppt download
ENDF/B-VII evaluated cross section for 157 Gd(n, γ ) reaction ...
ENDF/B-VII.0 product of neutron-capture cross section (at 30 keV in mb ...
PPT - ENDF/B-VIII.0 covariance testing at Oak Ridge National Laboratory ...
JEFF-3.1—ENDF/B-VII.0 U (n; ) cross section comparison. | Download ...
PPT - Decay Data Library In ENDF/B-VII Alejandro Sonzogni National ...
(PDF) ENDF/B-VII.1 ZR-90 Principal cross sections Cross section ...
Comparison of the microscopic cross section uncertainties between ...
Basic benchmarks used in the validation of the ENDF/B-VIII.0 library ...
(PDF) Progress towards the ENDF/B-VIII.1 release
Impact of specific isotope ENDF/B-VIII.0 neutron library on k e f f of ...
Neutron capture for 183 W compared to ENDF/B-VII evaluation. Many ...
Comparison of standard ENDF/B-VII.1 and ENDF/B-VII.1 + 157 ENEA ...
Angular distribution functions of JENDL-4.0/HE and ENDF/B-VII for the ...
Impact of the specific isotope library from ENDF/B-VIII.0 to k of oxide ...
ENDF/B-VIII.1: Updated Nuclear Data Library | PDF | Nuclear Fission ...
(PDF) Impact of the ENDF/B-VIII.0 library on MCNP6.2-computed ambient ...
Emission rates as reported and after normalization to ENDF/B-VI.0 ...
Uncertainty of graphite elastic scattering. (ENDF/B-VII.0 and ...
DPA cross-sections of 93 Nb in FENDL-3.1d, original ENDF/B-VII.1 ...
PPT - Actinide ENDF/B-VII Cross Section Evaluations & Validation ...
ENDFB-VII.0 238 U cross-sections for several reactions are illustrated ...
Comparison between ENDF/B-VII.0, JEFF-3.1, JENDL-3.3, ENDF/B-VI.8 and ...
Comparison of carbon capture cross section in ENDF/B releases ...
238 U(n,fiss) cross-section of ENDF/B-VI and VII (at 300 K). | Download ...
The ratio of the computed organ dose values using ENDF/B-V ...
⁵⁶Fe, ²³⁵U, and ²³⁸U capture cross sections of ENDF/B-VII.0 and ...
ENDF/B-VII.1 library 56 Fe(n, γ ) cross section covariances (Zerkin et ...
Comparison of the flux and reactivity for IFBA between ENDF/B-VII.1 and ...
Revised ENDF/B-VII covariance data for the capture cross section of 48 ...
27 Al(n,c) cross-section of ENDF/B-VI and VII (at 300 K). | Download ...
Fission cross-section of U-238 and their % difference to ENDF/B-VII.1 ...
ENDF/B-VIII.0 and TENDL-2015 r-process abundances. | Download ...
The ratio of the function k(Ee, Eν ) for 235 U using ENDFB/VII.1 ...
ENDF/B-VII.1 evaluated and measured 197 Au(n, γ) cross sections near ...
FTC calculated using ENDF/B-VI.8 and VII.0 libraries (3.9 GWD/tU ...
(PDF) An inter-comparison between ENDF/B-VIII.0-NECP-Atlas and ENDF/B ...
Comparison of 6 Li (n,t) cross section in ENDF/B releases. | Download ...
ENDF_百度百科
Neutron transmission data for 184 W compared to ENDF/B-VII evaluation ...
ENDF-B-VII.1-NNDC/README.md at main · openmc-data-storage/ENDF-B-VII.1 ...
²³⁵U and ²³⁸U fission cross sections of ENDF/B-VII.0 and ENDF/B-VII.1 ...
3: (n,γ) cross section of uranium-235 in ENDF/B-VIII (black) and ...
The mathematical ratio (red) between ENDF/B-VII.0 (blue) and JENDL-3.3 ...
MCS one-group (n, γ) cross sections (barns) Nuclide ENDF/B-VII.1 ...
Comparison of ENDF/B and JENDL 233 U evaluations for ORNL fast ...
[PDF] ENDF/B-VIII.0: The 8 th Major Release of the Nuclear Reaction ...
Capture cross section of the graphite for ENDF/B-VII.0 and ENDF/B-VII.1 ...
Energy dependent sensitivities of kinf of LEU fuel assembly for ...
(a) Cross-sections of 7 Li(p, n) 7 Be reaction in JENDL-4.0/HE ...
Comparison of 35 Cl (n,p) cross section in ENDF/B releases. | Download ...
TNCs values for the ENDF/B-VII.1, the ENDF/B-VIII and standards 2017 ...
(PDF) First Assessment of ENDF/B-VIII and EPICS Atomic Data Libraries
MCNPX (ENDFB-VII and LA150 libraries were used) simulated neutron ...
Nuclear Data Sensitivity Study for the EBR-II Fast Reactor Benchmark ...
ENDF/B-VII.1 library [Chadwick et al. 2011, 2887] evaluated and EXFOR ...
Fuel salt inventory in uranium and 233 U with ENDF/B-6, ENDF/B-7 and ...
The ENDF/B-VIII.0 238 U(n,f) cross section was adequately reproduced ...
Difference in reactivity between the ENDF/B-VII.1 versus the ...
Neutron cross-sections for 3 He from the ENDF/B-VII.0 evaluation ...
3: ENDF/B-VII.0, 2 and 6 group 239 94 Pu fission cross sections ...
ENDF-6 Formats Manual Data Formats and Procedures for the Evaluated ...
The ENDF/B-VI and JENDL3.3 evaluations of the | Download Scientific Diagram
ENDF/B-VII.1 Evaluated Nuclear Data Library
Ratio of thermal neutron fission cross sections for ENDF/B-VII.0 to ...
(PDF) Use of nickel sphere and copper cube with Cf neutron source in ...
Relative Differences between ENDF/B-VII.1 and ENDF/B-VIII.0 for 16 O ...
Relative differences between ENDF/B-VII.1 and ENDF/B-VIII.0 for 56 Fe ...
Comparison of fission cross section for ENDF/B-VI and ad hoc JENDL ...
Comparison between modeling results obtained using ENDF/B-VI and ...
The 197 Au(n, γ) cross section measured at n TOF [5] compared to the ...
Neutronic Characteristics of ENDF/B-VIII.0 Compared to ENDF/B-VII.1 for ...
16 O(n,α) in CIELO versus ENDF/B-VII.1, showing the higher cross ...
Table 5 from ENDF-6 Formats Manual Data Formats and Procedures for the ...
MARK III spectrum calculated with MCNP and 235 U PFNS from ENDF/B-VII.1 ...
Comparison between ENDF/B-VI and ENDF/B-VII simulated formation iron ...
(PDF) ENDF/B-VII.0: Next Generation Evaluated Nuclear Data Library for ...
Relative uncertainty of the ²³⁵U (n,γ) cross section in different ...
(PDF) PLANS FOR USE OF ENDF/B IN REACTOR RESEARCH IN INDONESIA
Table 3 from ENDF-6 Formats Manual Data Formats and Procedures for the ...
Fillable Online REPRODUCTION COPY ENDF/B-lV Fission-Product Files ...
(PDF) ENDF/B-VII.0 Data Testing for Three Fast Critical Assemblies
ENDF/B-VII.1 Decay Sublibrary
(PDF) A Study of the Covariance Data in ENDF/B VIII.0 for Low Z Isotopes
Figure 3 from Benchmark Analysis of a Prismatic Type-high Temperature ...
Figure 3 from Updates to the ORIGEN-S Data Libraries Using ENDF/B-VI ...
Figure 2 from ENDF-6 Formats Manual Data Formats and Procedures for the ...
Figure 5 from Accuracy Evaluation of Monte Carlo Simulation Results ...
(PDF) Evaluating the Uncertainty Effects of Carbon Nuclear Data on ...
JNE | Free Full-Text | Neutronic Characteristics of ENDF/B-VIII.0 ...
Full article: Development of a Coupled Depletion Perturbation Theory ...
(PDF) Uncovering Where Compensating Errors Could Hide in ENDF/B-VIII.0
ENDF-201: ENDF/B-VI summary documentation - Page 1 of 490 - UNT Digital ...
