Photonuclear cross-sections of233U using neutron capture gamma-rays, near threshold

1993 ◽  
Vol 106 (9) ◽  
pp. 1165-1173 ◽  
Author(s):  
M. A. P. V. de Moraes ◽  
M. F. Cesar
Keyword(s):  
Gamma Rays ◽  
Cross Sections ◽  
Neutron Capture ◽  
Near Threshold

Photonuclear cross sections of Pu-239 using neutron capture gamma rays, near threshold

1993 ◽  
Vol 47 (4) ◽  
pp. 519-523 ◽  
Author(s):  
Marco Antonio ◽  
P V de Moraes ◽  
Marilia F Cesar
Keyword(s):  
Gamma Rays ◽  
Cross Sections ◽  
Neutron Capture ◽  
Near Threshold

scholarly journals Partial and total thermal neutron capture cross sections for non-destructive assay and transmutation monitoring of 99Tc

2002 ◽  
Vol 90 (8) ◽  
Author(s):  
G. L. Molnár ◽  
T. Belgya ◽  
Zs. Révay ◽  
Syed M. Qaim
Keyword(s):  
Gamma Rays ◽  
Cross Sections ◽  
Neutron Capture ◽  
Gamma Ray ◽  
Cold Neutron ◽  
Production Cross ◽  
Radioactive Product ◽  
Non Destructive ◽  
Decay Gamma ◽  
Capture Cross Sections

SummaryAccurate partial gamma-ray production cross sections were determined for the prompt and radioactive product decay gamma rays following cold neutron capture in

NEUTRON CAPTURE GAMMA RAYS FROM LITHIUM, BORON, AND NITROGEN

1957 ◽  
Vol 35 (12) ◽  
pp. 1347-1360 ◽  
Author(s):  
G. A. Bartholomew ◽  
P. J. Campion
Keyword(s):  
Thermal Neutron ◽  
Gamma Rays ◽  
Cross Sections ◽  
Neutron Capture ◽  
Radiative Capture ◽  
Capture Cross ◽  
Γ Rays ◽  
Capture Cross Sections

The neutron capture γ-rays from Li7, B11, and N15 have been studied. In Li7 γ-rays are observed at 7.26 ± 0.03 Mev. and 6.78 ± 0.05 Mev. In B11 six γ-rays are detected. The spectrum is consistent with J = 7/2 + for the capturing state. In N15 six previously unreported γ-rays are detected. Estimates of thermal neutron radiative capture cross sections are: Li6, 0.028 ± 0.008 b.; B10, 0.5 ± 0.2 b.; and N14, 0.08 ± 0.02 b.

scholarly journals Improved STEREO simulation with a new gamma ray spectrum of excited gadolinium isotopes using FIFRELIN

2019 ◽  
Vol 55 (10) ◽  
Author(s):  
H. Almazán ◽  
L. Bernard ◽  
A. Blanchet ◽  
A. Bonhomme ◽  
C. Buck ◽  
...  
Keyword(s):  
Gamma Rays ◽  
Cross Sections ◽  
Neutron Capture ◽  
Gamma Ray ◽  
Detection Efficiency ◽  
Liquid Scintillator ◽  
Calibration Source ◽  
Active Volume ◽  
Capture Event ◽  
Excited Nuclei

Abstract. The STEREO experiment measures the electron antineutrino spectrum emitted in a research reactor using the inverse beta decay reaction on H nuclei in a gadolinium loaded liquid scintillator. The detection is based on a signal coincidence of a prompt positron and a delayed neutron capture event. The simulated response of the neutron capture on gadolinium is crucial for the comparison with data, in particular in the case of the detection efficiency. Among all stable isotopes, 155Gd and 157Gd have the highest cross sections for thermal neutron capture. The excited nuclei after the neutron capture emit gamma rays with a total energy of about 8MeV. The complex level schemes of 156Gd and 158Gd are a challenge for the modeling and prediction of the deexcitation spectrum, especially for compact detectors where gamma rays can escape the active volume. With a new description of the Gd (n,$ \gamma$γ) cascades obtained using the FIFRELIN code, the agreement between simulation and measurements with a neutron calibration source was significantly improved in the STEREO experiment. A database of ten millions of deexcitation cascades for each isotope has been generated and is now available for the user.

Angular distribution of Pu-239 photofission fragments near threshold, using neutron capture gamma rays

1992 ◽  
Vol 70 (12) ◽  
pp. 1232-1235
Author(s):  
Marco Antonio Proenca Vieira De Moraes ◽  
Marilia T. Cesar
Keyword(s):  
Angular Distribution ◽  
Thermal Neutron ◽  
Gamma Rays ◽  
Neutron Capture ◽  
Research Reactor ◽  
Angular Distributions ◽  
Lead Target ◽  
Thermal Neutron Capture ◽  
Excitation Energies ◽  
Near Threshold

The angular distribution of Pu-239 photofission fragments produced by thermal neutron capture gamma rays in two targets placed in the IEA-R1 (Instituto de Energia Atomica-Reator 1) research reactor were measured. Angular distributions of the form W(θ) = A + B sin2θ were observed for discrete excitation energies of 5.43 MeV (sulphur target) and 7.35 MeV (lead target). An anisotropy that corresponds to (B/A = −0.122 ± 0.036) was recorded for E = 5.43 MeV. The angular distribution for E = 7.35 MeV was practically isotropic: (B/A = −0.01 ± 0.02).

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