Reactor performance and safety characteristics of ThN-UN fuel concepts in a PWR

Gorton, Jacob P.; Collins, Benjamin; Nelson, Andrew T.; Brown, Nicholas R.

doi:10.1016/j.nucengdes.2019.110317

Cited by 19 publications

(8 citation statements)

References 33 publications

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“…(U,Pu)N) and composites are being considered as nuclear fuels or fuel components (e.g. tristructural isotropic particles) for advanced reactors such as liquid metal-cooled fast reactors and high-temperature gascooled reactors as well as light water reactors [27][28][29][30][31][32][33]. However, UN has unproven performance in accident scenarios, such as a fuel cladding breach where the fuel pellet would be exposed to water coolant or steam [34][35][36][37][38][39].…”

Section: Introductionmentioning

confidence: 99%

Phase and defect evolution in uranium-nitrogen-oxygen system under irradiation

Khafizov

Jiang

et al. 2021

Acta Materialia

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Section: Introductionmentioning

confidence: 99%

Phase and defect evolution in uranium-nitrogen-oxygen system under irradiation

Khafizov

Jiang

et al. 2021

Acta Materialia

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“…The porosity-corrected thermal conductivity is $10-15% lower than what is predicted from volume fraction calculations of each phase contribution to thermal conductivity. 16 This may be due to minor oxygen impurity, which has been shown to cause significant degradation of thermal conductivity in both UN and in UN + PuN nitride mixtures. 17,18 However, no apparent surface oxidation was observed prior to testing the samples.…”

Section: Thermal Conductivitymentioning

confidence: 99%

Thermophysical Properties of Mixtures of Thorium and Uranium Nitride

Parker

Newman

Fallgren

et al. 2021

JOM

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The miscibility, lattice parameter, and thermophysical properties of (Th0.2U0.8)N and (Th0.5U0.5)N have been investigated. It is shown that additions of thorium nitride (ThN) to uranium nitride (UN) increases the thermophysical performance of the mixed nitride fuel form in comparison to reference UN. In the more dilute limit, additions of ThN serve as a burnable neutronic poison and reduces the change in keff over the lifecycle of the fuel. At higher concentrations, additions of ThN serve as a significant fertile source of 233U. Where appropriate, comparisons to previous work on UN + PuN mixtures are made, as this is a comparable fuel form for potential fast reactor concepts, and a suitable point of contrast in the possible design space afforded by mixed (ThxU1 − x)N fuel forms. The data from this work are the input parameters for finite element modeling of the temperature distribution in a compact reactor. The results of modeling and simulation of this core design are shown for the case of steady-state operation and during double, adjacent heat pipe failure.

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“…In addition, thorium has a reproduction factor more significant than U-235 and Pu-239 in the thermal energy range, resulting in better fuel cycle performance in terms of conversion ratio. From nonproliferation point of view, the addition of thorium to the PWR results in less plutonium being produced [10]. The high internal conversion ratio of thorium-based fuels in the thermal reactor spectrum makes the use of this fuel very potential to realize long-lived reactors without on-site refueling [11].…”

Section: Introductionmentioning

confidence: 99%

Parametric Study of Thorium Fuel Utilization on Small Modular Pressurized Water Reactors (PWR)

Lapanporo

Su’ud

2022

J. Phys.: Conf. Ser.

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Small Modular Pressurized Water Reactor (PWR) can be used to overcome the problem of electricity shortages in remote areas with fewer populations. These reactors usually use uranium-based fuel. Currently, the use of thorium-based fuels for this type of reactor has received constant attention, leading to several investigations of fuel performance. This study aims to determine the performance of thorium-based fuel in the PWR core at a power level of 300 MWt. The analysis was carried out by varying the percentage of U-233 as fissile material in Thorium (Th-233U)O2 fuel by 3%-8% and Pa-231 variation as burnable poison 0.2%-5%. In addition, analysis of changes in the volume fraction of fuel ranging from 40%-60%, with the type of cladding used in the form of Zirlo. The calculation system uses the SRAC computer code with PIJ and CITATION modules for cell and core calculations, using JENDL-4.0 nuclide data. Parameters analyzed from the fuel cell calculation results are reactor criticality, excess reactivity, and power density profile. The analysis results show that the best fuel performance is found in fuel volume fraction of 60%, U-233 configuration on the fuel of 4-5-6%, and the addition of 2.5% Pa-231. This fuel configuration can achieve cycles of up to 19 years with excess reactivity at BOL of 2.57% dk/k and excess reactivity at EOL of 0.87% dk/k.

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Reactor performance and safety characteristics of ThN-UN fuel concepts in a PWR

Cited by 19 publications

References 33 publications

Phase and defect evolution in uranium-nitrogen-oxygen system under irradiation

Phase and defect evolution in uranium-nitrogen-oxygen system under irradiation

Thermophysical Properties of Mixtures of Thorium and Uranium Nitride

Parametric Study of Thorium Fuel Utilization on Small Modular Pressurized Water Reactors (PWR)

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