Study of neutron capture reaction-induced displacement damage cross section and KERMA factor

Author(s):  
Shengli Chen
2005 ◽  
Vol 6 (3) ◽  
pp. 283-286 ◽  
Author(s):  
Kazuyoshi Furutaka ◽  
Hideo Harada ◽  
Shoji Nakamura ◽  
Toshio Katoh ◽  
Toshiyuki Fujii ◽  
...  

1956 ◽  
Vol 34 (3) ◽  
pp. 238-245 ◽  
Author(s):  
L. P. Roy ◽  
L. Yaffe

Ce144 has been produced by the successive neutron capture reaction Ce142 (n, γ)Ce143(n, γ)Ce144. The pile neutron capture cross section of the 33 hr. Ce143 was determined by separating Pr144, the daughter of Ce144, from the rigorously-purified cerium at frequent intervals. The amount of Pr144 formed increased linearly with the square of the neutron flux in a manner consistent with that of a successive neutron capture reaction. The value for the pile neutron capture cross section of Ce143 was found to be 6.0 ± 0.7 barns.


2013 ◽  
Vol 2013 ◽  
pp. 1-10 ◽  
Author(s):  
C. Arenas ◽  
R. Bratton ◽  
F. Reventos ◽  
K. Ivanov

The study explored the calculation of uncertainty based on available cross-section covariance data and computational tool on fuel lattice levels, which included pin cell and the fuel assembly models. Uncertainty variations due to temperatures changes and different fuel compositions are the main focus of this analysis. Selected assemblies and unit pin cells were analyzed according to the OECD LWR UAM benchmark specifications. Criticality and uncertainty analysis were performed using TSUNAMI-2D sequence in SCALE 6.1. It was found that uncertainties increase with increasing temperature, whilekinfdecreases. This increase in the uncertainty is due to the increase in sensitivity of the largest contributing reaction of uncertainty, namely, the neutron capture reaction238U(n,γ) due to the Doppler broadening. In addition, three types (UOX, MOX, and UOX-Gd2O3) of fuel material compositions were analyzed. A remarkable increase in uncertainty inkinfwas observed for the case of MOX fuel. The increase in uncertainty ofkinfin MOX fuel was nearly twice the corresponding value in UOX fuel. The neutron-nuclide reaction of238U, mainly inelastic scattering (n,n′), contributed the most to the uncertainties in the MOX fuel, shifting the neutron spectrum to higher energy compared to the UOX fuel.


2020 ◽  
Vol 102 (6) ◽  
Author(s):  
C. Porzio ◽  
C. Michelagnoli ◽  
N. Cieplicka-Oryńczak ◽  
M. Sferrazza ◽  
S. Leoni ◽  
...  

2016 ◽  
Vol 947 ◽  
pp. 76-126 ◽  
Author(s):  
J. Bērziņš ◽  
T. Krasta ◽  
L. Simonova ◽  
M. Balodis ◽  
V. Bondarenko ◽  
...  

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