The utilization of thorium for long-life small thermal reactors without on-site refueling

Subki, Iyos; Pramutadi, Asril; Rida, S.N.M.; Su’ud, Zaki; Sapta, R. Eka; Nurul, S. Muh.; Topan, S.; Astuti, Yuli; Soentono, Soedyartomo

doi:10.1016/j.pnucene.2007.10.029

Cited by 14 publications

(9 citation statements)

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“…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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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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“…Besides that, many studies have been conducted to investigate the performance of thorium-based fuel used in PWR. It has been shown that Th-232 and U-233 oxide or (Th,U-233)O2 fuel has excellent performance to a long-life PWR, those are longer operation period without refueling, higher internal conversion ratio, and higher fuel burn-up (Subki et al, 2008;Subkhi et al, 2012;Subkhi et al, 2013;Subkhi et al, 2015;Hassan et al, 2020;Napirah & Su'ud, 2020;Lapanporo & Su'ud, 2022).…”

Section: Introductionmentioning

confidence: 99%

Comparative Study of UO2 and (Th,U-233)O2 Performance in Small Long-Life PWR Fuel Cell

Napirah

Su’ud

2022

J. Ilmu Fis.

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A study was performed comparing the performance of UO2 and (Th,U-233)O2 fuel in small long-life PWR. The neutronic calculation carried out by PIJ module of SRAC2006 was done to a fuel cell in 10 years of operation. The calculation was conducted by varying the enrichment of U-235 in UO2 and U-233 in (Th,U-233)O2 for 1% - 20% and also by varying the fuel volume fraction for 40%, 45%, 50%, 55%, and 60%. The performance was observed by comparing the enrichment needed by each fuel type to gain criticality in 10 years, the infinite multiplication factor (k-inf) value, and the conversion ratio (CR) value. The calculation results showed that 60% fuel volume fraction gave critical conditions with the lowest infinite multiplication factor and highest conversion ratio for both fuel types. While in terms of fissile nuclide enrichment needed, (Th,U-233)O2 had better performance than UO2, because only 5% U-233 was needed in (Th,U-233)O2 while UO2 needed 9% U-235 to gain criticality in 10 years of operation.

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“…Beforehand, neutronic analysis of GFR with SRAC2006 code system with modified CANDLE burnup scheme has been analyzed . And then the neutronic calculation of thorium fuel has been calculated before . The calculation is for thermal reactors, ie, high temperature gas cooled reactor, pressurized water reactor, and boiling water reactor.…”

Section: Introductionmentioning

confidence: 99%

“…[2][3][4][5][6][7][8][9] And then the neutronic calculation of thorium fuel has been calculated before. 10 The calculation is for thermal reactors, ie, high temperature gas cooled reactor, pressurized water reactor, and boiling water reactor. In this research, the neutronic calculation compares thorium nitride and uranium nitride fuel to operate long life without refueling for the fuel and less excess reactivity value (<2%Δk/k).…”

Section: Introductionmentioning

confidence: 99%

Comparison of uranium plutonium nitride (U-Pu-N) and thorium nitride (Th-N) fuel for 500 MWth gas-cooled fast reactor (GFR) long life without refueling

et al. 2017

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SummaryComparison of uranium plutonium nitride and thorium nitride fuel for 500 MWth gas-cooled fast reactor has been done. Gas-cooled fast reactor is one type of generation IV reactor that can be operated in high temperature. Due to the high temperature, it can be used in hydrogen production. In this study, we compare the neutronic analysis of two fuel types, ie, uranium nitride fuel (U,Pu)N and thorium nitride fuel (Th,U233)N. The neutronic calculation uses SRAC2006 code system, and the data libraries use JENDL4.0.First, the fuel pin calculation (PIJ calculation) has been done to take the macro data that are used in CITATION calculation. Both uranium and thorium fuel use heterogeneous configuration with 3 variation fuel in the core. F1 is located in the central core, F2 middle core, and F3 outer core.The variation of fuel fraction is 40% until 65%, cladding 10%, and coolant 25% until 40%. For (U,Pu)N fuel, the diameter of the active core is 220 cm, and the height of the active core is 110 cm. And for (Th,U233)N, the diameter of the active core is 250 cm and the height of the active core is 150 cm. The reflector radial-axial width is 50 cm. For uranium plutonium nitride fuel, the type of the fuel in one core is varied; ie, F1 is 8%, F2 is 10%, and F3 is 12%. For thorium nitride fuel, the type of the fuel in one core also varied; ie, F1 is 7.8%, F2 is 8%, and F3 is 8.8%. The optimum value of thorium nitride is when fuel fraction of region F1 = 60%, F2 = 57.5%, F3 = 60%, the burn up time up to 20 years without refueling, max k-eff value is 1.0109, and max excess reactivity value is 1.08%. Neutronic analysis shows that both uranium and thorium fuel have excess reactivity value less than 2% but thorium fuel has excess reactivity less than uranium nitride fuel.Uranium fuel has better breeding capability than thorium fuel. Therefore, it is better to use uranium fuel for fast reactor like GFR, which has high breeding capability.

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The utilization of thorium for long-life small thermal reactors without on-site refueling

Cited by 14 publications

References 0 publications

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

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

Comparative Study of UO2 and (Th,U-233)O2 Performance in Small Long-Life PWR Fuel Cell

Comparison of uranium plutonium nitride (U-Pu-N) and thorium nitride (Th-N) fuel for 500 MWth gas-cooled fast reactor (GFR) long life without refueling

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