Thorium

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Mayeen Uddin Khandaker - One of the best experts on this subject based on the ideXlab platform.

  • viability of Thorium based nuclear fuel cycle for the next generation nuclear reactor issues and prospects
    Renewable & Sustainable Energy Reviews, 2018
    Co-Authors: Uguru Edwin Humphrey, Mayeen Uddin Khandaker
    Abstract:

    Abstract This paper presented a review on the past, present and the future of Thorium fuel cycle. The aim of this study is to evaluate the developments in Thorium fuel cycle, looking at the prospects and drawbacks on the possibility of Thorium-based nuclear fuel for commercial reactors realising the increasing challenges of uranium-based nuclear fuel. The initial interest on Thorium-based nuclear fuel and why it was abandoned at the early stage of nuclear technology were considered. Also, the reasons behind the present renewed interest on the viability of Thorium fuel cycle as a valuable alternative to the conventional uranium-based fuel were studied. Thorium abundance, its physical, chemical and neutronic properties were evaluated in comparison to the uranium fuel cycle to determine Thorium fuel sustainability for next generation nuclear industry. In this study, it was found that Thorium fuel is three to four times more abundant, has higher conductivity, high melting temperature, low expansivity and more proliferation resistant compared to uranium fuel. The possible application and related challenges of Thorium fuels in different reactor types and designs such as light water reactors (LWRs), high temperature gas-cooled reactors (HTGRs), heavy water reactors (HWRs), molten salt reactors (MSRs) and accelerator driven system reactors (ADSRs) were reviewed. The findings indicate that Thorium fuel cycle can be used in the currently dominant LWRs designs in the nuclear industry with little technical modification, and also in other reactor types under investigation for future application especially molten salt breeder reactors, fast reactors and accelerator driven system reactors. Finally, this review made some recommendations on the short-term and long–term applications of Thorium-based nuclear fuel cycle, and the issues that must be addressed before using Thorium fuel for commercial reactor operations.

Suizheng Qiu - One of the best experts on this subject based on the ideXlab platform.

  • Coupled neutronics/thermal hydraulics evaluation for Thorium based fuels in thermal spectrum SCWR
    Progress in Nuclear Energy, 2013
    Co-Authors: Khurrum Saleem Chaudri, Wenxi Tian, Suizheng Qiu
    Abstract:

    Abstract Thorium can supplement the current limited reserves of uranium. In current study, analyses are performed for Thorium based fuels in thermal neutron spectrum Super Critical Water Reactor (SCWR). Thorium based fuels are studied in two roles. First role being replacement of conventional uranium dioxide fuel while the other being burner of Reactor Grade Plutonium (RG-Pu) in thermal neutron spectrum SCWR. Coupled neutron physics/thermal hydraulics analyses are performed due to large density variation of coolant over the active fuel length. Analyses reveal that Thorium-uranium MOX fuels lead to smaller burnup values as compared to equivalent enriched uranium dioxide but possess the advantage of smaller excess reactivity at Beginning of Life (BOL). This can lead to savings in the form of Burnable Poisons (BP). Smaller fuel average temperature values are obtained for Thorium-uranium MOX fuels as compared to uranium dioxide fuel option. Coated fuel option utilizing mixed Thorium-uranium mono nitride fuel can help further decrease fuel average temperature values for Thorium based fuels. U-233, produced in Thorium uranium fuels, contribution towards fission energy produced is smaller as compared to plutonium produced in conventional uranium dioxide fuel. In terms of proliferation resistance, approximately 40% less quantity of plutonium is produced for Thorium-uranium MOX fuels (for studied compositions) as compared to equivalent enriched uranium dioxide fuel. But, there is not much difference between the discharged plutonium vector compositions. Thorium–Plutonium based fuels lead to significantly harder spectrum which results in larger spread in radial power density and eventually causes larger values for thermal hydraulic parameters like fuel and clad temperature. Due to almost no production of plutonium, Thorium based fuels can be a very good option to burn RG-Pu in thermal spectrum SCWR. Thorium based fuels destroyed almost 74% initially loaded RG-Pu as compared to 60% for uranium based MOX. HEU based Thorium fuels can be a very good option for replacing conventional uranium dioxide fuels as very small quantities of plutonium is produced. This option, although, has regulatory issues due to use of HEU material.

J. Pérez - One of the best experts on this subject based on the ideXlab platform.

  • Evaluation of uranium Thorium and plutonium Thorium fuel cycles in a very high temperature hybrid system
    Progress in Nuclear Energy, 2013
    Co-Authors: C. García, J. Rosales, L. García, A. Muñoz, F. Rosales, C. Brayner, J. Pérez
    Abstract:

    Abstract In recent times, there is a renewed and additional interest in Thorium because of its interesting benefits. Thorium fuel cycle is an attractive way to produce long term nuclear energy with low radiotoxicity waste. In addition, the transition to Thorium could be done through the incineration of weapons grade plutonium or civilian plutonium. Th-based fuel cycles have intrinsic proliferation-resistance and Thorium is 3–4 times more abundant than uranium. Therefore, Thorium fuels can complement uranium fuels and ensure long term sustainability of nuclear power. In this paper, the main advantages of the use of fuel cycles based on uranium-Thorium and plutonium-Thorium fuel mixtures are evaluated in a hybrid system to reach the deep burn of the fuel. To reach this goal, the preliminary conceptual design of a hybrid system composed of a critical reactor and two Accelerated Driven Systems, of the type of very high temperature pebble-bed systems, moderated by graphite and cooled by gas, is analyzed. Uranium-Thorium and plutonium-Thorium once-through and two stages fuel cycles are evaluated. Several parameters describing fuel behaviour and minor actinide stockpile are compared for the analyzed cycles.

Uguru Edwin Humphrey - One of the best experts on this subject based on the ideXlab platform.

  • viability of Thorium based nuclear fuel cycle for the next generation nuclear reactor issues and prospects
    Renewable & Sustainable Energy Reviews, 2018
    Co-Authors: Uguru Edwin Humphrey, Mayeen Uddin Khandaker
    Abstract:

    Abstract This paper presented a review on the past, present and the future of Thorium fuel cycle. The aim of this study is to evaluate the developments in Thorium fuel cycle, looking at the prospects and drawbacks on the possibility of Thorium-based nuclear fuel for commercial reactors realising the increasing challenges of uranium-based nuclear fuel. The initial interest on Thorium-based nuclear fuel and why it was abandoned at the early stage of nuclear technology were considered. Also, the reasons behind the present renewed interest on the viability of Thorium fuel cycle as a valuable alternative to the conventional uranium-based fuel were studied. Thorium abundance, its physical, chemical and neutronic properties were evaluated in comparison to the uranium fuel cycle to determine Thorium fuel sustainability for next generation nuclear industry. In this study, it was found that Thorium fuel is three to four times more abundant, has higher conductivity, high melting temperature, low expansivity and more proliferation resistant compared to uranium fuel. The possible application and related challenges of Thorium fuels in different reactor types and designs such as light water reactors (LWRs), high temperature gas-cooled reactors (HTGRs), heavy water reactors (HWRs), molten salt reactors (MSRs) and accelerator driven system reactors (ADSRs) were reviewed. The findings indicate that Thorium fuel cycle can be used in the currently dominant LWRs designs in the nuclear industry with little technical modification, and also in other reactor types under investigation for future application especially molten salt breeder reactors, fast reactors and accelerator driven system reactors. Finally, this review made some recommendations on the short-term and long–term applications of Thorium-based nuclear fuel cycle, and the issues that must be addressed before using Thorium fuel for commercial reactor operations.

Khurrum Saleem Chaudri - One of the best experts on this subject based on the ideXlab platform.

  • Coupled neutronics/thermal hydraulics evaluation for Thorium based fuels in thermal spectrum SCWR
    Progress in Nuclear Energy, 2013
    Co-Authors: Khurrum Saleem Chaudri, Wenxi Tian, Suizheng Qiu
    Abstract:

    Abstract Thorium can supplement the current limited reserves of uranium. In current study, analyses are performed for Thorium based fuels in thermal neutron spectrum Super Critical Water Reactor (SCWR). Thorium based fuels are studied in two roles. First role being replacement of conventional uranium dioxide fuel while the other being burner of Reactor Grade Plutonium (RG-Pu) in thermal neutron spectrum SCWR. Coupled neutron physics/thermal hydraulics analyses are performed due to large density variation of coolant over the active fuel length. Analyses reveal that Thorium-uranium MOX fuels lead to smaller burnup values as compared to equivalent enriched uranium dioxide but possess the advantage of smaller excess reactivity at Beginning of Life (BOL). This can lead to savings in the form of Burnable Poisons (BP). Smaller fuel average temperature values are obtained for Thorium-uranium MOX fuels as compared to uranium dioxide fuel option. Coated fuel option utilizing mixed Thorium-uranium mono nitride fuel can help further decrease fuel average temperature values for Thorium based fuels. U-233, produced in Thorium uranium fuels, contribution towards fission energy produced is smaller as compared to plutonium produced in conventional uranium dioxide fuel. In terms of proliferation resistance, approximately 40% less quantity of plutonium is produced for Thorium-uranium MOX fuels (for studied compositions) as compared to equivalent enriched uranium dioxide fuel. But, there is not much difference between the discharged plutonium vector compositions. Thorium–Plutonium based fuels lead to significantly harder spectrum which results in larger spread in radial power density and eventually causes larger values for thermal hydraulic parameters like fuel and clad temperature. Due to almost no production of plutonium, Thorium based fuels can be a very good option to burn RG-Pu in thermal spectrum SCWR. Thorium based fuels destroyed almost 74% initially loaded RG-Pu as compared to 60% for uranium based MOX. HEU based Thorium fuels can be a very good option for replacing conventional uranium dioxide fuels as very small quantities of plutonium is produced. This option, although, has regulatory issues due to use of HEU material.