Determination of Resonance Parameters and their Covariances from Neutron Induced Reaction Cross Section Data

2012 ◽  
Vol 113 (12) ◽  
pp. 3054-3100 ◽  
Author(s):  
P. Schillebeeckx ◽  
B. Becker ◽  
Y. Danon ◽  
K. Guber ◽  
H. Harada ◽  
...  
Keyword(s):  
Cross Section ◽  
Reaction Cross Section ◽  
Reaction Cross ◽  
Cross Section Data ◽  
Resonance Parameters ◽  
Section Data ◽  
Induced Reaction

scholarly journals Measurement of the 234U(n,f) cross section in the energy range between 14.8 and 17.8 MeV using Micromegas detectors

2020 ◽  
Vol 239 ◽  
pp. 05005
Author(s):  
A. Kalamara ◽  
S. Chasapoglou ◽  
V. Michalopoulou ◽  
A. Stamatopoulos ◽  
Z. Eleme ◽  
...  
Keyword(s):  
Cross Section ◽  
Reaction Cross Section ◽  
Reaction Cross ◽  
Cross Section Data ◽  
Fission Yield ◽  
Active Mass ◽  
Section Data ◽  
Set Up ◽  
Reference Reaction

The 234U(n,f) reaction cross section was measured for three neutron energies 14.8, 16.5 and 17.8 MeV, relative to the238U(n,f) reference reaction. The in-beam measurements were carried out by using a set-up based on Micromegas detectors, while the quasi-monoenergetic neutron beams were produced by means of the 3H(d,n)4He reaction at the 5.5MV Tandem T11/25 Accelerator Laboratory of the National Center for Scientific Research "Demokritos" in Athens (Greece). Additionaly, α-spectroscopy measurements were performed in order to determine the active mass of the samples and the corresponding impurities. In order to estimate the fission-fragment detection efficiency, Monte Carlo simulations were carried out using the GEF and FLUKA codes. Furthermore, simulations were also performed by coupling the NeuSDesc and MCNP5 codes for the determination of the neutron energy distribution in all the irradiated samples and the results were used in order to correct for the contribution of low energy parasitic neutrons in the fission yield. The final cross section data are presented, along with the methodology adopted for the treatment of the parasitic neutrons.

An Am/Be neutron source and its use in integral tests of differential neutron reaction cross-section data

2010 ◽  
Vol 68 (9) ◽  
pp. 1656-1661 ◽  
Author(s):  
M.S. Uddin ◽  
M.R. Zaman ◽  
S.M. Hossain ◽  
I. Spahn ◽  
S. Sudár ◽  
...  
Keyword(s):  
Cross Section ◽  
Neutron Source ◽  
Reaction Cross Section ◽  
Reaction Cross ◽  
Cross Section Data ◽  
Section Data ◽  
Neutron Reaction
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