Radiation characteristics of palladium extracted from spent fuel of the BOR-60 reactor

1987 ◽  
Vol 63 (1) ◽  
pp. 509-512
Author(s):  
B. Ya. Shcherbakov ◽  
D. I. Evgrafova ◽  
V. I. Myshlyavkin ◽  
V. V. Ovechkin ◽  
�. Ya. Smetanin ◽  
...  
Keyword(s):  
Spent Fuel ◽  
Radiation Characteristics

Neutron radiation characteristics of the IVth generation reactor spent fuel

2018 ◽  
Author(s):  
Sergey Bedenko ◽  
Igor Shamanin ◽  
Victor Grachev ◽  
Vladimir Knyshev ◽  
Olesya Ukrainets ◽  
...  
Keyword(s):  
Neutron Radiation ◽  
Spent Fuel ◽  
Radiation Characteristics

scholarly journals Peculiarities of the radiation formation in dispersed microencapsulated nuclear fuel

2019 ◽  
Vol 5 (1) ◽  
pp. 23-29
Author(s):  
Sergey V. Bedenko ◽  
Vladimir V. Knyshev ◽  
Mariya Ye. Kuznetsova ◽  
Igor O. Lutsik ◽  
Igor V. Shamanin
Keyword(s):  
Nuclear Fuel ◽  
Computational Study ◽  
Reactor Core ◽  
Spectral Composition ◽  
Neutron Radiation ◽  
Photon Radiation ◽  
Structural Elements ◽  
Spent Fuel ◽  
Radiation Characteristics ◽  
Average Mass

A computational study has been performed for various options of the thorium reactor core loading. Neutronic studies of fuel have been conducted, its isotopic composition has been calculated, and the alpha emitters and the sources of neutron and photon radiation in the microencapsulated nuclear fuel have been analyzed. The studies had the purpose of developing the methodology used to estimate the radiation characteristics of nuclear fuel with a complex inner structure. Emphasis is placed on calculating the quantitative and spectral composition of the neutrons formed as the result of (a, n) reactions on small- and average-mass nuclei. The ratio of the quantity of the neutrons resulting from the (a, n) reactions to the quantity of the neutrons formed as the result of spontaneous fission has been calculated for fuel with heterogeneous and homogeneous arrangements of fissionable and structural elements. The developed tools will make it possible to estimate the neutron radiation dose, to revise the traditional fresh and spent fuel handling procedures, and to estimate, using the Rossi alpha method, the neutron multiplication factor in deeply subcritical systems. The neutron yield and spectrum were calculated using an analytical model and verified codes such as WIMS-D5B, ORIGEN-APP, SOURCES-4C and SRIM-2013.

End-to-end calculation of the radiation characteristics of VVER-1000 spent fuel assemblies

2012 ◽  
Vol 75 (13) ◽  
pp. 1603-1615 ◽  
Author(s):  
I. I. Linge ◽  
E. F. Mitenkova ◽  
N. V. Novikov
Keyword(s):  
Spent Fuel ◽  
Radiation Characteristics ◽  
Fuel Assemblies ◽  
End To End

THERMAL HYDRAULIC ANALYSIS OF SPENT FUEL SUBASSEMBLY DURING TRANSPORTATION FROM FBTR TO REPROCESSING FACILITY

Equipment ◽  
2006 ◽  
Author(s):  
D. Sujish ◽  
C. Meikandamurthy ◽  
T. R. Ellappan ◽  
M. Rajan ◽  
G. Vaidyanathan
Keyword(s):  
Spent Fuel ◽  
Hydraulic Analysis ◽  
Thermal Hydraulic Analysis
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