THE SPECTRUM OF NEUTRONS FROM THE IRRADIATION OF URANIUM BY 14-MEV NEUTRONS

1961 ◽  
Vol 39 (7) ◽  
pp. 957-966 ◽  
Author(s):  
R. L. Clarke

The spectrum and absolute yield of neutrons resulting from 14-Mev neutrons incident on natural uranium was observed at 90°± 16 to the incident neutron beam by a time-of-flight method. Further observations of the spectrum from 9 to 13.5 Mev were made for scattering angles at 30° and 60°. In addition to the expected neutrons resulting from evaporation and fission, strong evidence is seen for direct interaction inelastic scattering. The (n,n′) cross section is estimated to be 150 ± 70 millibarns.

2001 ◽  
Vol 34 (5) ◽  
pp. 613-624 ◽  
Author(s):  
C. R. Borlado ◽  
F. J. Mompean ◽  
Ru Lin Peng

A Monte Carlo code for the simulation of neutron strain scanning experiments on a reactor-based two-axis diffractometer is described. In order to validate this code, several experiments have been performed. A comparison is made between experimental and simulated results for instrumental resolution, primary beam divergence and wavelength distribution in the incident neutron beam. Finally, the application of the simulation results to the analysis of a real neutron strain scanning experiment is outlined.


Author(s):  
Roberto S. Pinna ◽  
Svemir Rudić ◽  
Matthew J. Capstick ◽  
David J. McPhail ◽  
Daniel E. Pooley ◽  
...  

2003 ◽  
Vol 36 (5) ◽  
pp. 1262-1265 ◽  
Author(s):  
A. N. Falcão ◽  
F. M. A. Margaça ◽  
F. G. Carvalho

A study of the contribution of the individual channels of a converging multichannel collimator to the operation of the device is carried out by means of a Monte Carlo computer simulation. The simulation shows that the coupling between the divergence of the incident neutron beam and the inclination of the individual CMC channel axis relative to the beam direction modulates the channel performance as far as intensity and resolution of the transmitted neutrons are concerned. While this does not impair in any significant way the usefulness of the device, the results are helpful to the designer.


2019 ◽  
Vol 24 ◽  
pp. 250
Author(s):  
A. Kanellakopoulos ◽  
A. Stamatopoulos ◽  
A. Tsinganis ◽  
M. Kokkoris ◽  
R. Vlastou ◽  
...  

The fission cross-section of 234U was measured at incident neutron energies between 300 and 500 keV and 4 and 5 MeV with a setup based on “microbulk” MicroMegas detectors. The standard 235,238U fission cross-sections were used as reference. The neutron beams were produced via the 7Li(p,n) and the 2H(d,n) reactions at the neutron beam facility of the 5.5 MeV Tandem accelerator laboratory at NCSR “Demokritos”. The mass of the actinide content of the targets used and of their impurities was quantitatively determined via α – spectroscopy. The developed methodology and preliminary results are presented.


2018 ◽  
Vol 1055 ◽  
pp. 012014 ◽  
Author(s):  
A Di Giulio ◽  
M Zanetti ◽  
G Romanelli ◽  
M Krzystyniak ◽  
R Senesi ◽  
...  

2019 ◽  
Vol 26 ◽  
pp. 166
Author(s):  
A. Kalamara ◽  
R. Vlastou ◽  
M. Kokkoris ◽  
N. Patronis ◽  
M. Serris ◽  
...  

The cross section of the 191Ir(n,2n) reaction was experimentally determined relative to the 27Al(n,α)24Na reference reaction one, for incident neutron beam energies ranging from 15.3 to 20.9 MeV, by means of the activation technique. The quasi-monoenergetic neutron beams were produced at the 5.5 MV Tandem Accelerator ofNCSR "Demokritos" via the 3H(d,n)4He reaction. Following the irradiations the activity induced by the neutron beam at the targets and reference foils was measured by HPGe detectors. The cross sections for the population of the second isomeric state (m2) of 190Ir and the sum of the ground and isomeric states (g+m1+0.086 m2) were independently determined. Additionally, theoretical calculations of the above cross sections were carried out using the EMPIRE code. The details of these calculations concerning the optical model parameters, are described in the present work.


Author(s):  
О. О. Грицай ◽  
А. К. Гримало ◽  
В. В. Колотий ◽  
В. М. Венедиктов ◽  
С. П. Волковецький ◽  
...  

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