Applications for Thorium in Multistage Fuel Cycles with Heavy Water Reactors

2018 ◽  
Vol 204 (1) ◽  
pp. 41-58
Author(s):  
Timothy Ault ◽  
Steven Krahn ◽  
Andrew Worrall ◽  
Allen Croff
2019 ◽  
Vol 8 (2) ◽  
pp. 109-130
Author(s):  
Alberto D. Mendoza España ◽  
Blair P. Bromley

To meet future global needs for energy and green technology, it is prudent to identify energy sources and technology that may potentially be economically beneficial. Thorium-based fuels with nuclear technology, such as the Canadian heavy-water reactor, have been proposed as a way to meet those global needs, though economic challenges persist in deploying thorium-based fuels. Therefore, economic strategies to overcome the economic challenges in deploying thorium-based fuels are needed. To identify potential strategies for advancing the deployment of thorium-based fuels, this paper conducts a historical examination of the economics of thorium fuel cycles to identify economic factors that can influence a country’s development of thorium-based fuel cycles. In particular, this paper reviews the economic issues associated with Canada’s experience in deploying thorium-based fuel cycles. The study finds that the existence of natural resources and the associated price, a nuclear fuel cycle’s costs, a country’s international trade balance position and economic growth policies, the profitability of the electrical power and nuclear industry, and the technical and economical characteristics of the nuclear reactor developed in a country may all influence the adoption of a thorium-based fuel cycle. Furthermore, recent advancements in developing thorium-based fuel cycles are suggested as a possible way of bridging the technical and economic gap between near-term and long-term implementation of thorium-based fuel cycles that may overcome current economic challenges.


1989 ◽  
Vol 67 (5) ◽  
pp. 787-794
Author(s):  
V. V. Vladimirskii ◽  
B. I. Il'ichev ◽  
G. N. Karavaev ◽  
M. L. Okhlopkov ◽  
V. V. Seliverstov
Keyword(s):  

2020 ◽  
Vol 6 (2) ◽  
pp. 131-135
Author(s):  
Vladimir A. Eliseev ◽  
Dmitry A. Klinov ◽  
Noël Camarcat ◽  
David Lemasson ◽  
Clement Mériot ◽  
...  

Accumulation of plutonium extracted from the spent nuclear fuel (SNF) of light water reactors is one of the central problems in nuclear power. To reduce out-of-the-reactor Pu inventory, leading nuclear power countries (France, Japan) use plutonium in light water power reactors in the form of MOX fuel, with half of Pu fissioning in this fuel. The rest of Pu cannot be reused easily and efficiently in light water reactors because of the high content of even isotopes. Plutonium for which there are no potential consumers is accumulated. Unlike thermal reactors, fast reactors take plutonium of any isotopic composition. That makes it possible to improve plutonium isotopic composition and to reduce the fraction of even isotopes to the level that allows reuse of such plutonium in thermal reactors. The idea of changing the isotopic composition of Pu in fast reactors is well-known. The originality of the research lies in applying this idea to combine the fuel cycles of fast and thermal reactors. Pu isotopic composition can be improved by combining certain operational activities in order to supply fuel to thermal and fast reactors. Scientific and technological justification of the possibility will let Russian BN technologies and French MOX fuel technologies work in synergy with thermal reactors.


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