Thermoluminescence dosimetry of a thermal neutron field and comparison with Monte Carlo calculations

2004 ◽  
Vol 111 (1) ◽  
pp. 35-39 ◽  
Author(s):  
A. C. Fernandes
Keyword(s):  
Monte Carlo ◽  
Thermal Neutron ◽  
Neutron Field ◽  
Monte Carlo Calculations ◽  
Thermoluminescence Dosimetry

Monte Carlo calculations of thermal neutron capture in gadolinium: A comparison of GEANT4 and MCNP with measurements

2006 ◽  
Vol 33 (2) ◽  
pp. 337-341 ◽  
Author(s):  
Shirin A. Enger ◽  
Per Munck af Rosenschöld ◽  
Arash Rezaei ◽  
Hans Lundqvist
Keyword(s):  
Monte Carlo ◽  
Thermal Neutron ◽  
Neutron Capture ◽  
Thermal Neutron Capture ◽  
Monte Carlo Calculations

Ranges of shielded nuclides from thermal-neutron fission

1969 ◽  
Vol 47 (21) ◽  
pp. 2371-2385 ◽  
Author(s):  
H. Nakahara ◽  
J. W. Harvey ◽  
G. E. Gordon
Keyword(s):  
Monte Carlo ◽  
Thermal Neutron ◽  
Neutron Emission ◽  
Fission Products ◽  
Energy Transformation ◽  
Neutron Fission ◽  
Monte Carlo Calculations ◽  
Neighboring Chain ◽  
Thermal Neutron Fission ◽  
Γ Ray

Average ranges in Al of shielded nuclides 86Rb and 136Cs and several chain-yield species from thermal-neutron fission of 233U and 235U have been measured. The values obtained (in mg/cm2 Al) are, for 233U: 86Rb, 3.88 ± 0.04; 136CS, 2.80 ± 0.01; and for 235U: 86Rb, 3.76 ± 0.03; 136Cs, 2.81 ± 0.01. A range–energy transformation was used to determine average kinetic energies [Formula: see text] of the secondary fragments. In agreement with previous work, the shielded nuclides are found to have smaller [Formula: see text] values than neighboring chain-yield species. The deficits of [Formula: see text] are, for 233U, 4 and 8 MeV, and for 235U, 8 and 10 MeV, respectively, for 86Rb and 136Cs. Most of the range experiments were done with the thick-catcher method followed by conventional radiochemical treatment of the catcher foils. Ranges of 20 products from 233U were determined in preliminary experiments in which gross γ-ray spectra of fission products in the catcher foils were observed with a Ge(Li) detector. The kinetic-energy deficits of the shielded species are interpreted by Monte Carlo calculations of prompt-neutron emission.

Monte Carlo calculations of neutron spectrum parameters at the JRTR NAA channels

2021 ◽  
Vol 134 ◽  
pp. 103688
Author(s):  
Ihsan Farouki ◽  
Rashdan Malkawi ◽  
Sayel Marashdeh
Keyword(s):  
Monte Carlo ◽  
Neutron Spectrum ◽  
Monte Carlo Calculations
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