The Status of Generation IV Sodium-Cooled Fast Reactor Technology Development and its Future Project

Ichimiya, Masashi

doi:10.1016/j.egypro.2011.06.011

Cited by 15 publications

(12 citation statements)

References 2 publications

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“…The SFR is the most promising reactor type because it can achieve the Generation IV goals in a reasonable amount of time, based on experience accumulated over the years 2 . Generation IV reactors have the potential to ensure safety, economic competitiveness, reduction in environmental burden, efficient utilization of resources, resistance to nuclear proliferation, and enhanced physical protection 3,4 . Recently, design and construction work have started on active advanced SFR research projects, such as the Advanced Sodium Technological Reactor for Industrial Demonstration (ASTRID) in France and Prototype Generation‐IV Sodium‐cooled Fast Reactor (PGSFR) in South Korea 5 .…”

Section: Introductionmentioning

confidence: 99%

“…Recently, design and construction work have started on active advanced SFR research projects, such as the Advanced Sodium Technological Reactor for Industrial Demonstration (ASTRID) in France and Prototype Generation‐IV Sodium‐cooled Fast Reactor (PGSFR) in South Korea 5 . The commercial Japan Sodium‐cooled Fast Reactor (JSFR) was included officially in their national plan with a start‐up target date of 2025 3 and operation target date of 2050 6 …”

Section: Introductionmentioning

confidence: 99%

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Neutronic analysis of sodium‐cooled fast reactor design with different fuel types using modified CANDLE shuffling strategy in a radial direction

et al. 2021

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Summary This study compares three fuel types using neutronic analysis for use in a sodium‐cooled fast reactor (SFR) design with a modified CANDLE (Constant Axial shape of Neutron flux, nuclide densities, and power shape During Life of Energy production) radial shuffling strategy. SFR is one type of generation IV reactor that is currently under investigation for commercial implementation. In this study, the SFR design utilizes natural uranium as the fuel input. The designed reactor core has a two‐dimensional cylindrical geometry for each fuel mixed oxide (MOX), uranium‐plutonium nitride ([U‐Pu]N), and uranium‐plutonium zirconium ([U‐Pu]Zr). A radial shuffling strategy, using natural uranium as the fuel input, is applied to the SFR to manage the nuclear fuel burn‐up process of the long‐life reactor. This strategy is called the modified CANDLE burn‐up scheme. The reactor core is divided into 10 regions with equal volume to represent the 10 years that the reactor operates without refueling. Initially, the first (innermost) region of the reactor core is filled with natural uranium fuel. The result of the burn‐up from the first region is then shuffled into the second region. The third region is the result of the burn‐up that is shuffled from the second region, and so on. This mechanism only requires natural uranium as the input for each 10‐year fuel cycle. In this study, the fuel movement scheme is examined for three fuels. Global neutronic parameters, such as the multiplication factors and burn‐up analyses, are observed and optimized. Overall, for an output power of 500 MWth and an active core radius of 110 cm and height of 210 cm, the study indicates that (U‐Pu)N is the optimal fuel to be applied in the SFR with a modified CANDLE burn‐up scheme. (U‐Pu)Zr reaches a critical condition at an output power of 500 MWth with an active core radius of 130 cm and a height of 210 cm; whereas criticality for MOX is achieved at an output power of 1500 MWth with an active core radius of 210 cm and a height of 210 cm.

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Section: Introductionmentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

Neutronic analysis of sodium‐cooled fast reactor design with different fuel types using modified CANDLE shuffling strategy in a radial direction

et al. 2021

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“… Liquid metal fast reactors that can be further divided into: o Sodium cooled fast reactors [15][16][17].…”

Section: Introductionmentioning

confidence: 99%

Innovative model of annular fuel design for lead-cooled fast reactors

Rowinski

White

Zhao

2015

Progress in Nuclear Energy

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“…As one of the six nuclear systems of generation IV, the sodium-cooled fast reactor (SFR) has attracted world attention due to its low nuclear waste, high security, and utilization efficiency of uranium. [1,[7][8][9][10] With the development of nuclear power technology, higher requirements for the materials used in SFR have been brought forward. For example, as one of the key components in SFR, the guide tube of the control rod should possess excellent nuclear performance, high strength and ductility, as well as great hot corrosion resistance under the service environment of neutron irradiation, continuous impact, and liquid sodium at 250-560 °C.…”

mentioning

confidence: 99%

The Role of Strain and Dynamic Recrystallization During Hot Deformation of a Fe–Ni–Cr‐Based Alloy

Wang

Qin

et al. 2022

Adv Eng Mater

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The fossil fuel power plant is the dominant method for the generation of electricity around the world at present. [1] However, the combustion of fossil fuels, especially coal combustion, emits a large amount of CO 2 , NO x , and SO x , which aggravates the greenhouse effect and environmental pollution. [2][3][4][5][6] The development of nuclear power is necessary to reduce the environmental pollution and alleviate fossil energy crisis. From the 1950s to the present, nuclear power technology has evolved to generation IV. As one of the six nuclear systems of generation IV, the sodium-cooled fast reactor (SFR) has attracted world attention due to its low nuclear waste, high security, and utilization efficiency of uranium. [1,[7][8][9][10] With the development of nuclear power technology, higher requirements for the materials used in SFR have been brought forward. For example, as one of the key components in SFR, the guide tube of the control rod should possess excellent nuclear performance, high strength and ductility, as well as great hot corrosion resistance under the service environment of neutron irradiation, continuous impact, and liquid sodium at 250-560 °C. [11] The solution-strengthening superalloy with good combination properties can fulfil the requirements of the guide tube. The microstructure of the guide tube should be fine and uniform to ensure the high security of the nuclear power plant. However, the various tube thicknesses leads to complicated processing technology (forging, punching, hot extrusion, and hot rolling) for guide tube. The investigated alloy in this article is a solutionstrengthening superalloy used in the nuclear power plant.The previous studies about materials used in nuclear power plants mainly focused on the irradiation damage. Zhang et al. [12] investigated the effects of irradiation dose on the microstructure damages, including lattice defects, cavities, and stability of precipitates, in Inconel X-750 at elevated temperatures. Jin et al. [13] and Wan et al. [14] studied the evolution of the precipitates (γ 0 and γ 00 ) and the dislocation-precipitates interaction in Inconel 718 alloy under irradiation conditions. The sizes of γ 0 and γ 00 were smaller and the structure of γ 0 and γ 00 became disordered with the increasing irradiation dose. The dislocation-precipitates (γ 00 ) interaction under irradiation conditions led to the appearance of dislocation cells composed of precipitates, trailing dislocations, and dislocation loops. Meanwhile, the stress corrosion damage of Inconel 718 alloy in pressurized water reactor service was investigated by Leonard. [15] In addition, Mathew et al. [16] and Bhaduri et al. [17] studied the mechanical properties (tensile, creep, fatigue, and creep-fatigue interaction) of 316 LN SS alloy used in SFR. Nevertheless, the hot working of the nuclear power plant materials has been ignored. Meanwhile, the superalloy possesses high deformation resistance due to the solid strengthening effect by Cr, Mo, and other elements. [18][19][20] It is difficult to ca...

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The Status of Generation IV Sodium-Cooled Fast Reactor Technology Development and its Future Project

Cited by 15 publications

References 2 publications

Neutronic analysis of sodium‐cooled fast reactor design with different fuel types using modified CANDLE shuffling strategy in a radial direction

Neutronic analysis of sodium‐cooled fast reactor design with different fuel types using modified CANDLE shuffling strategy in a radial direction

Innovative model of annular fuel design for lead-cooled fast reactors

The Role of Strain and Dynamic Recrystallization During Hot Deformation of a Fe–Ni–Cr‐Based Alloy

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