The fourth version of the Japanese Evaluated Nuclear Data Library has been produced in cooperation with the Japanese Nuclear Data Committee. In the new library, much emphasis is placed on the impro...

https://www.tandfonline.com/doi/pdf/10.1080/18811248.2011.9711675

JENDL-4.0: A New Library for Nuclear Science and Engineering

The joint evaluated fission and fusion nuclear data library 3.3 is described. New evaluations for neutron-induced interactions with the major actinides $^{235}\hbox {U}$, $^{238}\hbox {U}$ and $^{239}\hbox {Pu}$, on $^{241}\hbox {Am}$ and $^{23}\hbox {Na}$, $^{59}\hbox {Ni}$, Cr, Cu, Zr, Cd, Hf, W, Au, Pb and Bi are presented. It includes new fission yields, prompt fission neutron spectra and average number of neutrons per fission. In addition, new data for radioactive decay, thermal neutron scattering, gamma-ray emission, neutron activation, delayed neutrons and displacement damage are presented. JEFF-3.3 was complemented by files from the TENDL project. The libraries for photon, proton, deuteron, triton, helion and alpha-particle induced reactions are from TENDL-2017. The demands for uncertainty quantification in modeling led to many new covariance data for the evaluations. A comparison between results from model calculations using the JEFF-3.3 library and those from benchmark experiments for criticality, delayed neutron yields, shielding and decay heat, reveals that JEFF-3.3 performes very well for a wide range of nuclear technology applications, in particular nuclear energy.

/pdf/the-joint-evaluated-fission-and-fusion-nuclear-data-library-3xawwctw8e.pdf

The joint evaluated fission and fusion nuclear data library, JEFF-3.3

Neutron Cross Sections Prepared by the United States Atomic Energy Commission (Selected Reference Material on Atomic Energy) Pp viii + 328 (London: McGraw-Hill Publishing Company, Ltd, 1955) 90s

/pdf/neutron-cross-sections-1bmmld6x38.pdf

Neutron Cross-Sections

Neutron capture and transmission measurements were performed by the time-of-flight technique at the Rensselaer Polytechnic Institute linac facility using metallic and liquid Gd samples. The liquid ...

/pdf/neutron-capture-and-total-cross-section-measurements-and-3xz2i9v94m.pdf

Neutron Capture and Total Cross-Section Measurements and Resonance Parameters of Gadolinium

The purpose of the present work is to accurately measure the neutron cross sections of samarium. The most significant isotope is {sup 149}Sm, which has a large neutron absorption cross section at thermal energies and is a {sup 235}U fission product with a 1% yield. Its cross sections are thus of concern to reactor neutronics. Neutron capture and transmission measurements were performed by the time-of-flight technique at the Rensselaer Polytechnic institute (RPI) LINAC facility using metallic and liquid Sm samples. The capture measurements were made at the 25 meter flight station with a multiplicity-type capture detector, and the transmission total cross-section measurements were performed at 15- and 25-meter flight stations with {sup 6}Li glass scintillation detectors. Resonance parameters were determined by a combined analysis of six experiments (three capture and three transmission) using the multi-level R-matrix Bayesian code SAMMY version M2. The significant features of this work are as follows. Dilute samples of samarium nitrate in deuterated water (D{sub 2}O) were prepared to measure the strong resonances at 0.1 and 8 eV without saturation. Disk-shaped spectroscopic quartz cells were obtained with parallel inner surfaces to provide a uniform thickness of solution. The diluent feature of the SAMMY program was usedmore » to analyze these data. The SAMMY program also includes multiple scattering corrections to capture yield data and resolution functions specific to the RPI facility. Resonance parameters for all stable isotopes of samarium were deduced for all resonances up to 30 eV. Thermal capture cross-section and capture resonance integral calculations were made using the resultant resonance parameters and were compared to results obtained using resonance parameters from ENDF/B-VI updated through release 3. Extending the definition of the capture resonance integral to include the strong 0.1 eV resonance in {sup 149}Sm, present measurements agree within estimated uncertainties with EnDF/B-VI release 3. The thermal capture cross-section was calculated from the present measurements of the resonance parameters and also agrees with ENDF within estimated uncertainties. The present measurements reduce the statistical uncertainties in resonance parameters compared to prior measurements.« less

/pdf/neutron-capture-and-transmission-measurements-and-resonance-3mtaunruqy.pdf

Neutron capture and transmission measurements and resonance parameter analysis of niobium

The focus of this work is to determine the resonance parameters for stable hafnium isotopes in the 0.005- to 200-eV region, with special emphasis on the overlapping 176Hf and 178Hf resonances near ...

/pdf/hafnium-resonance-parameter-analysis-using-neutron-capture-4jo8yesx45.pdf

Hafnium Resonance Parameter Analysis Using Neutron Capture and Transmission Experiments

The electron linear accelerator facility at the Rensselaer Polytechnic Institute was used to explore neutron interactions with molybdenum in the energy region from 10 eV to 2 keV. Neutron capture and transmission measurements were performed by the time-of-flight technique. Resonance parameters were extracted from the data using the multilevel R-matrix Bayesian code SAMMY. A table of resonance parameters and their uncertainties is presented. Two transmission measurements were performed at a flight path of 25 m with a 6 Li glass scintillation detector. The neutron capture measurements were per- formed at a flight path of 25 m with a 16-segment sodium iodide multiplicity detector. Nine different thicknesses of elemental molybdenum metal samples ranging from 0.051 mm (0.002 in.) to 6.35 mm (0.250 in.) were measured in either capture or transmission. Reductions in resonance integrals were observed when compared to ENDF/B-VII.0 for six of the seven stable isotopes. The largest reductions were 9% in 97 Mo and 11% in 100 Mo. The one measured increase in resonance integral relative to ENDF/B-VII.0 occurred in 95 Mo, and it was significant (10%). The measured distribution of neutron widths for 95 Mo and 97 Mo are a better match to a Porter-Thomas distribution than those of ENDF/B-VII.0. Neutron strength functions for 95 Mo and 97 Mo were measured and compared to ENDF/B-VII.0. The strength of 95 Mo and 97 Mo are within uncertainties of each other. The measured radiation width distribution for 95 Mo and 97 Mo are compared to those of ENDF/B-VII.0 and to x 2 distributions. Significant aspects of this analysis are the assignment of radiation widths, the determination of the transmission resolution function, and the propa- gation of experimental uncertainties into resonance parameter uncertainties.

/pdf/resonance-parameters-and-uncertainties-derived-from-4de8njzbiu.pdf

Resonance Parameters and Uncertainties Derived from Epithermal Neutron Capture and Transmission Measurements of Natural Molybdenum

Neutron capture and transmission measurements were performed by the time-of-flight tech- nique at the Rensselaer Polytechnic Institute LINAC using metallic zirconium samples. The capture mea- surement was made at the 25-m flight station with a multiplicity-type capture detector, and the transmission total cross-section measurements were performed at the 25-m flight station with a 6 Li glass scintillation detector. Resonance parameters were determined by a combined analysis of all 11 data sets (4 capture and 7 transmission) using the least-squares multilevel R-matrix code REFIT. The present measurements were undertaken to resolve discrepancies between common usage (ENDF/ B-VI) and the recent measurements of Salah et al. for the 300-eV zirconium doublet. The present measure- ments support the Salah et al. conclusions. Specifically, the results confirm the assignment of J 3 for the 91 Zr 292.5-eV resonance and include all significant resonances up to 2.5 keV. The zirconium reso- nance parametersGg and Gn, determined in the present measurement, are compared with the ENDF/B-VI parameters.

Neutron capture and total cross-section measurements and resonance parameter analysis of zirconium up to 2.5 keV

The Rensselaer Polytechnic Institute linear accelerator with the enhanced thermal target was used for neutron transmission measurements of rare earth metal samples of holmium, erbium, and thulium and isotopically enriched oxide samples of 166 Er2O3 and 167 Er2O3 in the energy range from 0.001 to 20 eV. The measurements were done with a 15-m time-of-flight spectrometer and provided high-quality data in the thermal and subthermal region as well as in the low energy resonance region. The effect of paramag- netic scattering on these cross sections is discussed. The data were corrected for paramagnetic scattering, and resonance parameters were obtained by fitting the transmission with the SAMMY multilevel R-matrix code. These results were compared to the ENDF0B-VI evaluation and to other measurements.

/pdf/neutron-total-cross-section-measurements-and-resonance-3aeywj54ow.pdf

Neutron Total Cross-Section Measurements and Resonance Parameter Analysis of Holmium, Thulium, and Erbium from 0.001 to 20 eV

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Papers

Hafnium Resonance Parameter Analysis Using Neutron Capture and Transmission Experiments

Resonance Parameters and Uncertainties Derived from Epithermal Neutron Capture and Transmission Measurements of Natural Molybdenum

Neutron capture and total cross-section measurements and resonance parameter analysis of zirconium up to 2.5 keV

Neutron Total Cross-Section Measurements and Resonance Parameter Analysis of Holmium, Thulium, and Erbium from 0.001 to 20 eV