scholarly journals Evaluation of spectral shift controlled reactors operating on the uranium fuel cycle. Final report

1979 ◽  
Author(s):  
R. A. Matzie ◽  
F. M. Sider
Keyword(s):  
Fuel Cycle ◽  
Spectral Shift ◽  
Final Report ◽  
Uranium Fuel

About the Thermal Hydraulic Analysis Part of a Coupled Study on a Thorium-Fueled SCWR Concept

2020 ◽  
Vol 6 (3) ◽  
Author(s):  
Attila Kiss ◽  
Béla Hegyesi ◽  
Patrik Richárd Ujváry ◽  
András Szabolcs Ványi ◽  
Gyula Csom
Keyword(s):  
Fuel Cycle ◽  
Three Dimensional ◽  
Spectral Shift ◽  
Average Density ◽  
Study Phase ◽  
Cfd Analysis ◽  
Axial Distribution ◽  
Cfd Models ◽  
Water Reactors ◽  
Uranium Plutonium

Abstract Inherently poorer moderation in supercritical water-cooled reactors (SCWRs) due to average density lower than in light water reactors and the resulted spectral shift can be useful when we apply thorium fuel-cycle instead of uranium–plutonium one, according to an ongoing study in Budapest University of Technology and Economics (BME) Institute of Nuclear Techniques (NTI). Upon this conclusion, a thorium-fueled SCWR design (Th-SCWR) has been proposed by BME NTI. In the current feasibility study phase, detailed three-dimensional (3D) computational fluid dynamics (CFD) calculations with novel neutronics analysis were coupled and conducted separately. Neutronics calculations provided the distribution of heat source, while the CFD analysis gave back axial distribution of coolant density (this iteration was repeated until an acceptable convergence). This paper presents the CFD analysis on thermal hydraulics of the initial design (two CFD models without any spacer device and one model with wrapped wire spacer) of Th-SCWR fuel assembly. As results of the preliminary design of Th-SCWR cladding wall, coolant and fuel temperatures have been determined; the flow field with and without spacer device has been showed, and the application of wrapped wire spacer has been proposed.

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

scholarly journals Fuel cycle and neutronic performance of a spectral shift molten salt reactor design

2018 ◽  
Vol 119 ◽  
pp. 396-410 ◽  
Author(s):  
Benjamin R. Betzler ◽  
Sean Robertson ◽  
Eva E. Davidson (née Sunny) ◽  
Jeffrey J. Powers ◽  
Andrew Worrall ◽  
...  
Keyword(s):  
Molten Salt ◽  
Fuel Cycle ◽  
Reactor Design ◽  
Spectral Shift ◽  
Molten Salt Reactor ◽  
Neutronic Performance
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