scholarly journals Environmental survey of the uranium fuel cycle

1974 ◽  
Author(s):  
Keyword(s):  
Fuel Cycle ◽  
Environmental Survey ◽  
Uranium Fuel

ICONE19-43519 Preliminary Research on Thorium-Uranium Fuel Cycle Characteristic in PWR

2011 ◽  
Vol 2011.19 (0) ◽  
pp. _ICONE1943-_ICONE1943
Author(s):  
Chunlin Wei ◽  
Xiuan Shi ◽  
Yongwei Yang ◽  
Zhiwei Zhou
Keyword(s):  
Fuel Cycle ◽  
Uranium Fuel ◽  
Preliminary Research

Parametric Lattice Study of a Graphite-Moderated Molten Salt Reactor

2015 ◽  
Vol 1 (1) ◽  
Author(s):  
Boris A. Hombourger ◽  
Jiří Křepel ◽  
Konstantin Mikityuk ◽  
Andreas Pautz
Keyword(s):  
Molten Salt ◽  
Fuel Cycle ◽  
Block Size ◽  
Equilibrium Composition ◽  
Reaction Rates ◽  
Point Of View ◽  
Fission Rate ◽  
Slowing Down ◽  
Channel Radius ◽  
Uranium Fuel

Molten salt reactors (MSRs) are promising advanced nuclear reactors for closure of the fuel cycle. This paper discusses the core design of graphite-moderated MSRs, thanks to a parametric study of the fuel and moderator lattice. The study is conducted at equilibrium of the thorium-uranium fuel cycle for several fuel channel radius and moderator block size combinations. The equilibrium composition for each studied configuration is derived with the help of an in-house MATLAB code, EQL0D, which uses the Serpent 2 Monte Carlo neutronics code for the calculation of reaction rates. The results include excess reactivity at equilibrium, mirroring the breeding gain, and the actinide vector composition for each configuration. Moreover, the occurence of an optimum of the excess reactivity per percent uranium-233 was observed. The investigations showed that it is systematically seen at an interchannel distance equal to the neutron slowing-down length in graphite for each configuration and does not depend on the salt channel radius beyond a certain size, which is given by the thermal fission rate reaching the levels of the fast fission rate. In this way, an exotic energy and spatial distribution of the neutrons are attained. The investigations highlight the potential attractiveness, from a neutronics/fuel cycle point of view, of both large fuel channels and moderators with a shorter neutron slowing-down length.

Burn up Study of an Innovative Natural Uranium-Thorium Fueled Reprocessing Free Fusion-Fission Hybrid Reactor Blanket with Closed Thorium-Uranium Fuel Cycle

2015 ◽  
Vol 68 (3) ◽  
pp. 566-572 ◽  
Author(s):  
S. C. Xiao ◽  
Jing Zhao ◽  
X. Heng ◽  
X. Y. Sheng ◽  
Z. Zhou ◽  
...  
Keyword(s):  
Fuel Cycle ◽  
Natural Uranium ◽  
Hybrid Reactor ◽  
Uranium Fuel

Potentiometric determination of uranium in phosphate-perchlorate medium and its applicability in the natural uranium fuel cycle

1986 ◽  
Vol 99 (2) ◽  
pp. 397-406 ◽  
Author(s):  
A. K. Pandey ◽  
R. C. Sharma ◽  
R. H. Iyer
Keyword(s):  
Fuel Cycle ◽  
Natural Uranium ◽  
Potentiometric Determination ◽  
Uranium Fuel

Breeding of 233U in the thorium–uranium fuel cycle in VVER reactors using heavy water

2015 ◽  
Vol 78 (11) ◽  
pp. 1274-1286 ◽  
Author(s):  
V. E. Marshalkin ◽  
V. M. Povyshev
Keyword(s):  
Heavy Water ◽  
Fuel Cycle ◽  
Uranium Fuel

scholarly journals Occupational safety data and casualty rates for the uranium fuel cycle. [Glossaries]

1981 ◽  
Author(s):  
F.R. O'Donnell ◽  
H.C. Hoy
Keyword(s):  
Occupational Safety ◽  
Fuel Cycle ◽  
Safety Data ◽  
Uranium Fuel
Sign in / Sign up

Export Citation Format

Share Document