Cross-sections for (n, 2n), (n, p), and (n, ?) reactions averaged over the neutron fission spectrum

1968 ◽  
Vol 25 (5) ◽  
pp. 1251-1253 ◽  
Author(s):  
F. Nasyrov
Keyword(s):  
Cross Sections ◽  
Neutron Fission ◽  
Fission Spectrum ◽  
Neutron Fission Spectrum

scholarly journals Transuranics Transmutation Using Neutrons Spectrum from Spallation Reactions

2015 ◽  
Vol 2015 ◽  
pp. 1-23 ◽  
Author(s):  
Maurício Gilberti ◽  
Claubia Pereira ◽  
Maria Auxiliadora F. Veloso ◽  
Antonella Lombardi Costa
Keyword(s):  
Simple Model ◽  
Neutron Spectrum ◽  
Hybrid System ◽  
Target Material ◽  
Neutron Fission ◽  
Spallation Target ◽  
Transport Code ◽  
Spallation Reactions ◽  
Fission Spectrum ◽  
Neutron Fission Spectrum

The aim is to analyse the neutron spectrum influence in a hybrid system ADS-fission inducing transuranics (TRUs) transmutation. A simple model consisting of an Accelerator-Driven Subcritical (ADS) system containing spallation target, moderator or coolant, and spheres of actinides, “fuel,” at different locations in the system was modelled. The simulation was performed using the MCNPX 2.6.0 particles transport code evaluating capture(n,γ)and fission(n,f)reactions, as well as the burnup of actinides. The goal is to examine the behaviour and influences of the hard neutron spectrum from spallation reactions in the transmutation, without the contribution or interference of multiplier subcritical medium, and compare the results with those obtained from the neutron fission spectrum. The results show that the transmutation efficiency is independent of the spallation target material used, and the neutrons spectrum from spallation does not contribute to increased rates of actinides transmutation even in the vicinity of the target.

Simulating the neutron-fission spectrum with a Po-Be source

1969 ◽  
Vol 27 (2) ◽  
pp. 876-877
Author(s):  
V. A. Kryzhanovskii ◽  
V. V. Terekhin
Keyword(s):  
Neutron Fission ◽  
Fission Spectrum ◽  
Neutron Fission Spectrum

Measurements of Neutron Fission Cross Sections of237Np,240Pu,241Pu,242Pu,244Pu, and241Am at 14.7 MeV

1986 ◽  
Vol 94 (1) ◽  
pp. 42-45 ◽  
Author(s):  
K. Gul ◽  
M. Ahmad ◽  
M. Anwar ◽  
S. M. Saleem
Keyword(s):  
Cross Sections ◽  
Neutron Fission

Average reaction cross sections in235U fission spectrum

1977 ◽  
Vol 43 (4) ◽  
pp. 914-914 ◽  
Author(s):  
E. I. Grigor'ev ◽  
V. P. Yaryna
Keyword(s):  
Cross Sections ◽  
Reaction Cross ◽  
Fission Spectrum ◽  
Reaction Cross Sections

Inelastic cross-sections for fission-spectrum neutrons—II

1956 ◽  
Vol 3 (4) ◽  
pp. 273-300
Author(s):  
H.A. Bethe ◽  
J.R. Beyster ◽  
R.E. Carter
Keyword(s):  
Cross Sections ◽  
Fission Spectrum

Integral measurement of spectrum-averaged cross sections of a few threshold reactions induced by fast neutrons of a TRIGA reactor: comparison with integrated data from excitation functions given in various data libraries

2020 ◽  
Vol 108 (7) ◽  
pp. 511-516
Author(s):  
Md. Shuza Uddin ◽  
K. A. Rafee ◽  
S. M. Hossain ◽  
R. Khan ◽  
S. M. Qaim
Keyword(s):  
Excitation Function ◽  
Cross Sections ◽  
Fast Neutrons ◽  
Integral Test ◽  
Triga Reactor ◽  
Fission Spectrum ◽  
Data Libraries ◽  
First Time ◽  
Prompt Fission ◽  
Fast Neutron Spectrum

AbstractIntegral cross sections of the reactions 24Mg(n,p)24Na, 27Al(n,p)27Mg, 27Al(n,α)24Na, 58Ni(n,d + np)57Co and 60Ni(n,p)60Co were measured for the first time using the fast neutron spectrum of a TRIGA reactor extending from 0.5 to 20 MeV. The values obtained in this work were comparable with the recommended values for a pure 235U prompt fission spectrum. The measured integral value was utilized for integral test of excitation function of each reaction given in some data libraries, namely ENDF/B-VIII.0, TENDL-2017, IRDFF-1.05 and ROSFOND-2010. The integral measurements are generally consistent with the integrated values within 5 %, except for a few cases, e. g. the reaction 60Ni(n,p)60Co, where the data libraries appear to need improvement.

scholarly journals Fission Product Mass Yield Curves and Their Energy Dependence

1976 ◽  
Vol 29 (3) ◽  
pp. 125 ◽  
Author(s):  
JL Cook ◽  
EK Rose ◽  
GD Trimble
Keyword(s):  
Fission Product ◽  
Saddle Point ◽  
Empirical Analysis ◽  
Energy Dependence ◽  
Cross Sections ◽  
Mass Yield ◽  
Neutron Fission ◽  
Yield Curves ◽  
Nuclear Temperature ◽  
Better Than

It has been found that the mass yield curves for 232Th, 233U, 235U, 238U and 239pU neutron fission can be fitted, with an accuracy of better than 20 %, by the superposition of two pairs of asymmetric gaussian curves and a single symmetric gaussian curve. The parameters of the fit have been investigated as a function of the nuclear temperature at the saddle point of the fissioning compound nucleus, and the widths and positions are found to vary linearly with this temperature. In addition, broad peaks are found in the weights of the gaussians, the weights being related to partial fission cross sections. This empirical analysis has been compared with the predictions of the Nix (1969) model of fission and deficiencies in the existing theory are discussed.

Inelastic cross-sections for fission-spectrum neutrons—III

1957 ◽  
Vol 4 (1) ◽  
pp. 3-25 ◽  
Author(s):  
H.A. Bethe ◽  
J.R. Beyster ◽  
R.E. Carter
Keyword(s):  
Cross Sections ◽  
Fission Spectrum
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