JRC data for the Ti-48 standard

A measurement of the 48Ti(n,n’gamma)48Ti reaction was performed at the GELINA neutron source of EC-JRC-IRMM using the GAINS spectrometer with the purpose of establishing a new gamma-ray standard for neutron induced cross section measurements. A natural target was used and the gamma-production cross section was measured for 10 transitions in the neutron energy range 0-18 MeV. The lowest achieved uncertainty was 4.8%.JRC.D.4-Standards for Nuclear Safety, Security and Safeguard

usion and breakup fusion of 6Li with 194Pt at energies around coulomb barrier

Results for fusion and breakup fusion reaction ( 6 Li+ 194 Pt) are presented and compared with other experimental data and model calculations. A strong isotopic effect is observed when comparing our data with results from ( 6 Li+ 198 Pt

Neutron inelastic cross section measurements for 24Mg

The gamma production cross sections from the neutron inelastic scattering on 24Mg were measured for neutron energies up to 18 MeV at GELINA (Geel Linear Accelerator), the neutron source operated by EC-JRC-IRMM, Belgium. The level cross section and the total inelastic cross section were determined. We used the GAINS (Gamma Array for Inelastic Neutron Scattering) spectrometer with 7 large volume HPGe detectors placed at 110◦ and 150◦ with respect to the beam direction. The neutron flux was determined with a 235U fission chamber. The results are compared with calculations performed with the TALYS 1.6 code using the default settings.JRC.D.4-Standards for Nuclear Safety, Security and Safeguard

Cross-section measurements for the 56Fe(n, xnγ) reactions

A measurement was performed at the white neutron source Geel Linear Accelerator (GELINA) of the Institute for Reference Materials and Measurements to determine the cross sections for the (n, n'γ ) and (n, 2n'γ ) reactions on 56Fe. The Gamma Array for Inelastic Neutron Scattering (GAINS) was used. The results are scaled to the neutron-induced fission cross section of 235U. The paper emphasizes the multiple checks performed to assure the consistency of the results. γ production cross sections, total inelastic cross sections, and level production cross sections were determined. A good agreement exists with previous measurements. Theoretical calculations were performed with the TALYS 1.6 reaction code using default parameters, but also using a microscopic approach. These calculations are discussed in comparison to the experimental data.JRC.D.4-Standards for Nuclear Safety, Security and Safeguard

Neutron inelastic cross section measurements on 58,60Ni

A natural nickel sample was used at the GELINA (Geel Electron LINear Accelerator) neutron source of the European Commission, Joint Research Centre, Geel to measure the neutron inelastic cross sections. The GAINS (Gamma Array for Inelastic Neutron Scattering) spectrometer was employed to detect the emitted gamma rays while a 235U fission chamber monitored the neutron flux. We report the preliminary production cross sections corresponding to the first transitions in 58,60Ni in comparison with previously reported data and with TALYS 1.9 calculations performed using the default input parameters.JRC.G.2-Standards for Nuclear Safety, Security and Safeguard

GAINS: neutron inelastic cross section measurements of interest for applications and reaction studies

The paper represents an overview of the measurements performed using the GAINS spectrometer at the GELINA neutron source at JRC-Geel in Belgium. The setup produced over the years highly precise cross sections while undergoing continuous upgrades. Our measurements are primarily driven by technological needs with an emphasis on structural materials used in the development of nuclear facilities. However, most cases offered the opportunity to investigate various reaction mechanism and/or nuclear structure issues. The second part of the paper concentrates on several specific experiments describing the particular difficulties we met and the solutions we adopted to infer reliable data and to draw significant conclusions.JRC.G.2-Standards for Nuclear Safety, Security and Safeguard

Cross-section measurements for the 57Fe(n, nγ)57Fe and 57Fe(n, 2nγ)56Fe reactions

A neutron inelastic scattering experiment was performed on an enriched 57Fe sample at the Geel Electron Linear Accelerator neutron source using the Gamma Array for Neutron Inelastic Scattering spectrometer. Several γ-production cross sections were determined, but the first transition (14.4 keV) could not be detected owing to the steadily increased γ background at low energies. Consequently, we use an interplay between experimental data and carefully tuned theoretical calculations to generate the total inelastic cross section.JRC.G.2-Standards for Nuclear Safety, Security and Safeguard

The limits of the GAINS spectrometer

The Gamma Array for Neutron Inelastic Scattering (GAINS) is currently operating at the GELINA (Geel Linear Accelerator) neutron source producing highly precise neutron inelastic scattering data. A series of recent investigations explored the limits of the experimental setup and technique. Measurements on 12C and 57Fe attempted the determination of very high and very low energy gamma production cross sections, respectively. An extended analysis was directed towards the generation of covariance matrices specifically for this experimental approach.JRC.D.4-Standards for Nuclear Safety, Security and Safeguard