scholarly journals Spent nuclear fuel project surface area estimates for N-Reactor fuel in the K East basin

1996 ◽  
Author(s):  
T.D. Cooper
Keyword(s):  
Surface Area ◽  
Nuclear Fuel ◽  
Spent Nuclear Fuel ◽  
Reactor Fuel

Studies of sorption of Th and Np on UO2 and TiO2

2000 ◽  
Vol 663 ◽  
Author(s):  
Yngve Albinsson ◽  
Hans Nilsson ◽  
Anna-Maria Jakobsson
Keyword(s):  
Distribution Coefficient ◽  
Surface Area ◽  
Nuclear Fuel ◽  
Spent Nuclear Fuel ◽  
No Reduction ◽  
Hydrogen Atmosphere ◽  
High Extent ◽  
The Moment ◽  
Tetravalent State ◽  
Pentavalent State

ABSTRACTWhen designing an underground repository for spent nuclear fuel it is important to know if and to what extent Np and Pu are reduced. At the moment only Np has been studied, but further investigations with Pu are planned.Np in the pentavalent state and Th in the tetravalent state (234Th, about 10−9 M) have been used to study the sorption onto TiO2 (no reduction is expected) and onto UO2 with different atmospheres (air, nitrogen and nitrogen and hydrogen at 5 MPa pressure), and with different Np- concentrations (about 10−12M, 239Np and 10−6 M,237Np).Th is sorbed to a high extent at pH>3 on both TiO2 and UO2. The sorption increases 3 orders of magnitude over one pH-unit when log Ka (the distribution coefficient with respect to surface area) is plotted against pH.The Np sorption on TiO2 is independent of the Np concentration and shows a slope of one when pH is plotted against log Ka. The higher sorption of Np onto UO2 compared with TiO2 indicates that Np is partially reduced even when it is in contact with air. No large differences can be observed for Np between the nitrogen and hydrogen-atmosphere, indicating that the absence of oxygen is the important factor for the reduction. The different Np concentrations had no great impact on the reduction/sorption on UO2.

scholarly journals Estimation of the Amounts of Curium and Americium Isotopes in SNF of the BN-600 Reactor

2018 ◽  
Vol 3 (3) ◽  
pp. 460
Author(s):  
E.I. Lukyan ◽  
G.L. Khorasanov ◽  
А.М. Terekhova
Keyword(s):  
Fuel Assembly ◽  
Nuclear Fuel ◽  
Spent Nuclear Fuel ◽  
Physical Characteristics ◽  
Reactor Fuel ◽  
Minor Actinides ◽  
Software Complex ◽  
Reactor Fuel Assembly

The neutron-physical characteristics of curium and americium in spent nuclear fuel (SNF) of the BN-600 reactor were considered in the work. With the help of the Serpent software complex, several models of the BN-600 reactor fuel assembly with different enrichment of fuel by U-235 were built. In BN-600, with the probability of dividing Am-241 by no more than 15%, incomplete burning of minor actinides (MA) occurs and even the accumulation of Cm-244, which is dangerous for storage.

Convective processes in spent nuclear fuel canisters

2002 ◽  
Author(s):  
Glenn E. McCreery ◽  
Keith G. Condie ◽  
Randy C. Clarksean ◽  
Donald M. McEligot
Keyword(s):  
Nuclear Fuel ◽  
Spent Nuclear Fuel ◽  
Convective Processes ◽  
Nuclear Fuel Canisters

A new approach to spent nuclear fuel recycling for light water reactors in the frame of remix concept

2020 ◽  
Vol 2020 (1) ◽  
pp. 67-77
Author(s):  
Nikita Vladimirivich Kovalyov ◽  
Boris Yakovlevich Zilberman ◽  
Nikolay Dmitrievich Goletskiy ◽  
Andrey Borisovich Sinyukhin
Keyword(s):  
Nuclear Fuel ◽  
Spent Nuclear Fuel ◽  
Light Water Reactors ◽  
New Approach ◽  
Light Water ◽  
Water Reactors
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