Achieving Resource Sustainability in China Through the Thorium Fuel Cycle in the Candu Reactor

2010 ◽  
Author(s):  
Peter G. Boczar ◽  
Bronwyn Hyland ◽  
Keith Bradley ◽  
Sermet Kuran
Keyword(s):  
Fuel Cycle ◽  
Close Approach ◽  
Natural Uranium ◽  
Fissile Material ◽  
Energy Potential ◽  
Candu Reactors ◽  
Fuel Cycles ◽  
Resource Sustainability ◽  
Enriched Uranium

The CANDU® reactor is the most resource-efficient reactor commercially available. The features that enable the CANDU reactor to utilize natural uranium facilitate the use of a wide variety of thorium fuel cycles. In the short term, the initial fissile material would be provided in a “mixed bundle”, in which low-enriched uranium (LEU) would comprise the outer two rings of a CANFLEX® bundle, with ThO2 in the central 8 elements. This cycle is economical, both in terms of fuel utilization and fuel cycle costs. The medium term strategy would be defined by the availability of plutonium and recovered uranium from reprocessed used LWR fuel. The plutonium could be used in Pu/Th bundles in the CANDU reactor, further increasing the energy derived from the thorium. Recovered uranium could also be effectively utilized in CANDU reactors. In the long term, the full energy potential from thorium could be realized through the recycle of the U-233 (and thorium) in the used CANDU fuel. Plutonium would only be required to top up the fissile content to achieve the desired burnup. Further improvements to the CANDU neutron economy could make possible a very close approach to the Self-Sufficient Equilibrium Thorium (SSET) cycle with a conversion ratio of unity, which would be completely self-sufficient in fissile material (recycled U-233).

Variants of the Perspective Closed Fuel Cycle, Based on REMIX-Technology

2014 ◽  
Author(s):  
Evgeniy Bobrov ◽  
Pavel Teplov ◽  
Pavel Alekseev ◽  
Alexander Chibinyaev ◽  
Anatoliy Dudnikox
Keyword(s):  
Fuel Cycle ◽  
Raw Materials ◽  
Natural Uranium ◽  
Depleted Uranium ◽  
Raw Material ◽  
Fissile Material ◽  
Spent Fuel ◽  
Closed Fuel Cycle ◽  
New Variant ◽  
Enriched Uranium

In the traditional closed fuel cycle, based on REMIX-technology (REgenerated MIXture of U and Pu oxides) the fuel composition is produced on the basis of a uranium and plutonium mixture from spent Light Water Reactor (LWR) fuel and additional natural uranium. In this case, there is some saving in the amount of natural uranium used. The basic features of the WWER-1000 fuel loadings with a new variant REMIX-fuel during multiple recycle in the closed nuclear fuel cycle are described in this paper. Such fuel compositions are produced on a basis of a uranium and plutonium mixture allocated at processing the spent fuel after irradiation in the WWER-1000 core, depleted uranium and fission material such as: 235U as a part of high-enriched uranium from the warheads superfluous for defense. Also here variants are considered of the perspective closed fuel cycle in which fissile feed materials for fuel manufacture is produced in the blankets of fast breeder reactors. The fissile material is 233U or Pu. The raw material is depleted uranium from the stocks of enrichment factories, or thorium. Natural uranium is not used in this case. The minimum feed material required for the REMIX technology in a closed fuel cycle was determined through calculations of different types of fissile and raw materials, with different cycle lengths and fuel-water ratios.

scholarly journals Optimization of the self-sufficient thorium fuel cycle for CANDU power reactors

2008 ◽  
Vol 23 (1) ◽  
pp. 3-10
Author(s):  
Boris Bergelson ◽  
Alexander Gerasimov ◽  
Georgy Tikhomirov
Keyword(s):  
New Technologies ◽  
Fuel Cycle ◽  
Fission Products ◽  
The Self ◽  
Fissile Material ◽  
Heavy Nuclei ◽  
Candu Reactors ◽  
Mode Of Operation ◽  
Enriched Uranium ◽  
Thorium Cycle

The results of optimization calculations for CANDU reactors operating in the thorium cycle are presented in this paper. Calculations were performed to validate the feasibility of operating a heavy-water thermal neutron power reactor in a self-sufficient thorium cycle. Two modes of operation were considered in the paper: the mode of preliminary accumulation of 233U in the reactor itself and the mode of operation in a self-sufficient cycle. For the mode of accumulation of 233U, it was assumed that enriched uranium or plutonium was used as additional fissile material to provide neutrons for 233U production. In the self-sufficient mode of operation, the mass and isotopic composition of heavy nuclei unloaded from the reactor should provide (after the removal of fission products) the value of the multiplication factor of the cell in the following cycle K>1. Additionally, the task was to determine the geometry and composition of the cell for an acceptable burn up of 233U. The results obtained demonstrate that the realization of a self-sufficient thorium mode for a CANDU reactor is possible without using new technologies. The main features of the reactor ensuring a self-sufficient mode of operation are a good neutron balance and moving of fuel through the active core.

CAREM X INPRO Case Study

2004 ◽  
Author(s):  
Pablo C. Florido ◽  
Dari´o Delmastro ◽  
Daniel Brasnarof ◽  
Osvaldo E. Azpitarte
Keyword(s):  
Nuclear Reactor ◽  
Fuel Cycle ◽  
High Level Waste ◽  
Fuel Cycles ◽  
Surface Intermediate ◽  
Geological Repository ◽  
Enriched Uranium ◽  
Intermediate Storage ◽  
High Level

Argentina is performing CAREM X Nuclear System Case Study based on CAREM nuclear reactor and Once Through Fuel Cycle, using SIGMA for enriched uranium production, and a deep geological repository for final disposal of high level waste after surface intermediate storage in horizontal natural convection silos, to verify INPRO (International Project on Innovative Nuclear Reactors and Fuel Cycles) methodology. Projections show that developing countries could play a crucial role in the deployment of nuclear energy, in the next fifty years. This case study will be highly useful for checking INPRO methodology for this scenario. In this contribution to ICONE 12, the preliminary findings of the Case Study are presented, including proposals to improve the INPRO methodology.

Overview of the U.S. Department of Energy Advanced Waste Forms Development

2018 ◽  
Author(s):  
Kimberly Gray ◽  
John Vienna ◽  
Patricia Paviet
Keyword(s):  
Nuclear Fuel ◽  
Fuel Cycle ◽  
Nuclear Fuel Cycle ◽  
The United States ◽  
Department Of Energy ◽  
High Level Waste ◽  
Fuel Cycles ◽  
Waste Forms ◽  
The U.S

In order to maintain the U.S. domestic nuclear capability, its scientific technical leadership, and to keep our options open for closing the nuclear fuel cycle, the Department of Energy, Office of Nuclear Energy (DOE-NE) invests in various R&D programs to identify and resolve technical challenges related to the sustainability of the nuclear fuel cycle. Sustainable fuel cycles are those that improve uranium resource utilization, maximize energy generation, minimize waste generation, improve safety and limit proliferation risk. DOE-NE chartered a Study on the evaluation and screening of nuclear fuel cycle options, to provide information about the potential benefits and challenges of nuclear fuel cycle options and to identify a relatively small number of promising fuel cycle options with the potential for achieving substantial improvements compared to the current nuclear fuel cycle in the United States. The identification of these promising fuel cycles helps in focusing and strengthening the U.S. R&D investment needed to support the set of promising fuel cycle system options and nuclear material management approaches. DOE-NE is developing and evaluating advanced technologies for the immobilization of waste issued from aqueous and electrochemical recycling activities including off-gas treatment and advanced fuel fabrication. The long-term scope of waste form development and performance activities includes not only the development, demonstration, and technical maturation of advanced waste management concepts but also the development and parameterization of defensible models to predict the long-term performance of waste forms in geologic disposal. Along with the finding of the Evaluation and Screening Study will be presented the major research efforts that are underway for the development and demonstration of waste forms and processes including glass ceramic for high-level waste raffinate, alloy waste forms and glass ceramics composites for HLW from the electrochemical processing of fast reactor fuels, and high durability waste forms for radioiodine.

scholarly journals A new approach to the recycling of spent nuclear fuel in thermal reactors within the REMIX concept

2020 ◽  
Vol 6 (2) ◽  
pp. 93-98
Author(s):  
Nikita V. Kovalev ◽  
Boris Ya. Zilberman ◽  
Nikolay D. Goletsky ◽  
Andrey B. Sinyukhin
Keyword(s):  
Nuclear Fuel ◽  
Spent Nuclear Fuel ◽  
Fuel Cycle ◽  
Nuclear Fuel Cycle ◽  
Natural Uranium ◽  
Spent Fuel ◽  
High Concentration ◽  
Energy Potential ◽  
New Approach ◽  
Reprocessed Uranium

A review of simulated nuclear fuel cycles with mixed uranium-plutonium fuel (REMIX) was carried out. The concept of REMIX fuel is one of the options for closing the nuclear fuel cycle (NFC), which makes it possible to recycle uranium and plutonium in VVER-1000/1200 thermal reactors at a 100% core loading. The authors propose a new approach to the recycling of spent nuclear fuel (SNF) in thermal reactors. The approach implies a simplified fabrication of mixed fuel when plutonium is used in high concentration together with enriched natural uranium, while reprocessed uranium is supposed to be enriched and used separately. The share of standard enriched natural uranium fuel in this nuclear fuel cycle is more than 50%, the share of mixed natU+Pu fuel is 25%, the rest is fuel obtained from enriched reprocessed uranium. It is emphasized that the new approach has the maximum economic prospect and makes it possible to organize the fabrication of this fuel and nuclear material cross-cycling at the facilities available in the Russian Federation in the short term. This NFC option eliminates the accumulation of SNF in the form of spent fuel assemblies (SFA). SNF is always reprocessed with the aim of further using the primary reprocessed uranium and plutonium. Non-recyclable in thermal reactors, burnt, reprocessed uranium, the energy potential of which is comparable to natural uranium, as well as secondary plutonium intended for further use in fast reactors, are sent as reprocessing by-products to the storage area.

Future Fuel Cycles: A Global Perspective

2008 ◽  
Author(s):  
Romney B. Duffey
Keyword(s):  
Heavy Water ◽  
Nuclear Power ◽  
Fuel Cycle ◽  
Global Perspective ◽  
Nuclear Power Reactor ◽  
Energy Futures ◽  
Fuel Cycles ◽  
Reactor Technology ◽  
Heavy Water Reactor ◽  
Enriched Uranium

Nuclear energy must be made available, freely and readily, to help meet world energy needs. The perspective offered here is a model for others to consider, adopting and adapting using whatever elements fit their own strategies and needs. The underlying philosophy is to retain flexibility in the reactor development, deployment and fuel cycle, while ensuring the principle that customer, energy market, safety, non-proliferation and sustainability needs are all addressed. Canada is the world’s largest exporter of uranium, providing about one-third of the world supply for nuclear power reactors. Canada’s Atomic Energy of Canada Limited (AECL) has developed a unique world-class nuclear power reactor technology — the CANDU® reactor based on the Pressure Tube Reactor (PTR) concept, moderated by heavy water (D2O), also sometimes called the Pressurized Heavy Water reactor or PHWR. With expectations of significant expansion in nuclear power programs worldwide and the resultant concerns about uranium availability and price, there is a growing desire to improve resource utilization by extracting more energy from each tonne of mined fissionable material. Attention is therefore being increasingly focused on fuel cycles that are more energy efficient, reduce waste streams and ensure sustainable futures. There are also many compelling reasons to utilize advanced fuel cycles in PTR (CANDU-type) thermal spectrum reactors. Because of its inherent technical characteristics, PTRs have a great deal of fuel cycle flexibility. The combination of relatively high neutron efficiency (provided by heavy water moderation and careful selection of core materials), on-line fuelling capability and simple fuel bundle design mean that PTR reactors can use not only natural and enriched uranium, but also a wide variety of other fuels including thorium-based fuels and those resulting from the recycle of irradiated fuel. In addition, the PTR can be optimized as a very effective “intermediate burner” to provide efficient fuel cycles that remove residual minor actinides. This inherent fuel cycle flexibility offers many technical, resource and sustainability, and economic advantages over other reactor technologies and is the subject of this paper. The design evolution and intent is to be consistent with improved or enhanced safety, licensing and operating limits and global proliferation concerns, and sustainable energy futures.

Advanced Fuel CANDU Reactor (AFCR) Core Physics With High-Burnup Recycled Uranium and Uranium-Thorium Fuel

2013 ◽  
Author(s):  
Mustapha Boubcher ◽  
Zhiliang Meng ◽  
Catherine M. Cottrell ◽  
Sermet Kuran
Keyword(s):  
Alternative Fuels ◽  
Fuel Cycle ◽  
Minimal Risk ◽  
Spent Fuel ◽  
Fuel Cycles ◽  
Fuel Bundle ◽  
Short Run ◽  
Advanced Fuel ◽  
Enriched Uranium ◽  
High Neutron

The CANDU reactor has flexibility for using alternative fuels, such as Recycled Uranium (RU), low-enriched uranium and thorium (LEU/Th) and plutonium-thorium (Pu/Th) based fuels. This capability results from a versatile pressure tube design, simple fuel bundle, on-power refuelling, and high neutron economy. The Advanced Fuel CANDU Reactor (AFCR), which retains the excellent neutron economy and fuel cycle flexibility that are inherent in the CANDU reactor design, is a design jointly undertaken by Candu Energy and its Chinese partners led by CNNC. The objective is to use RU that is planned to be available from the reprocessing of Chinese LWR fleet spent fuel and increase the overall uranium utilization at minimal cost and minimal risk at commercially proven CANDU type new build reactors. This paper is focused on various physics aspects of using RU and LEU/Th in the AFCR units in the short run. It also describes full-core management simulations for the implementation of DRU and LEU/Th fuel cycles in AFCR reactor. The CANFLEX bundle design was chosen as carrier for both DRU and LEU/Th fuel in this study.

AFCR and EC6: The Two Sister Products

2013 ◽  
Author(s):  
Frank Yee ◽  
Sermet Kuran ◽  
Mike Soulard ◽  
Zhenhua Zhang
Keyword(s):  
Reactor Core ◽  
Alternative Fuel ◽  
Natural Uranium ◽  
Implementation Plan ◽  
Candu Reactors ◽  
Fuel Cycles ◽  
Design Basis ◽  
Design Changes ◽  
Advanced Fuel ◽  
The Common

Candu Energy, based on its highly successful CANDU 6 (C6) reactors proven on four continents, is preparing to launch its C6 referenced Generation III products: Enhanced CANDU 6 (EC6), the natural uranium optimized, and Advanced Fuel CANDU Reactor (AFCR), the alternative fuel optimized, CANDU reactors. The AFCR design is based on the EC6 design with appropriate design changes to the reactor core to cater for the alternative fuel cycles and post Fukushima improvement.. The paper reviews the common design basis of these reactors and then discusses the unique advantages and market specific features for each product. The AFCR implementation plan for China is also discussed.

scholarly journals ON THE USE OF A CENTRAL THORIUM FUEL ELEMENT IN PRESSURE-TUBE HEAVY-WATER REACTOR FUEL BUNDLES

2018 ◽  
Vol 7 (2) ◽  
pp. 147-155 ◽  
Author(s):  
Michael McDonald ◽  
Megan Moore ◽  
Dan Wojtaszek ◽  
Nicholas Chornoboy ◽  
Geoffrey Edwards
Keyword(s):  
Fuel Element ◽  
Heavy Water ◽  
Fuel Cycle ◽  
Natural Uranium ◽  
Pressure Tube ◽  
Slight Reduction ◽  
Energy Potential ◽  
Thorium Dioxide ◽  
Water Reactor ◽  
Heavy Water Reactor

An incremental approach to introducing thorium to the conventional pressure-tube heavy-water reactor natural uranium fuel cycle is investigated. The approach involves the replacement of the centre fuel element of the bundle with an element of thorium dioxide. Increasing the operating margin of a key safety parameter, the coolant void reactivity, is a prime motivating factor. The analyses showed that the simple use of a single pin of thorium is unlikely to be economically advantageous due to a large burnup penalty and increased fuel costs. However, a slight reduction in the void reactivity is observed, and this approach does allow the exploitation of the energy potential available in thorium as an alternative nuclear fuel resource through the development of a U-233 resource. This bundle concept may also be advantageous from a fuel disposal point of view, as the fuel requires less time in storage before emplacement in a deep geological repository.

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