Metal Fuel Development and Verification for Prototype Generation IV Sodium-Cooled Fast Reactor

Lee, Chan Bock; Cheon, Jin-Sik; Kim, Sung Hoon; Park, Jeong-Yong; Joo, Hyung-Kook

doi:10.1016/j.net.2016.08.001

Cited by 28 publications

(10 citation statements)

References 18 publications

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“…Ferritic-martensitic (FM) steels are considered to be promising candidates for fuel cladding and duct materials for SFRs owing to their high thermal conductivities, low expansion coefficients, and superior irradiation swelling compared to that of austenitic steels [8][9][10]. However, the creep rupture strength of FM steels abruptly decreases during the long-term creep exposure at high temperatures [11].…”

Section: Introductionmentioning

confidence: 99%

Influence of Heat Treatment on the Workability of Modified 9Cr-2W Steel with Higher B Content

Heo

Kim

et al. 2019

Metals

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In this study, the effect of heat treatment on the fracture behavior of alloy B steel with boron (B) contents as high as 130 ppm was investigated. The Alloy B are derived from Gr.92 steel with outstanding creep characteristics. The amounts of minor alloying elements such as B, N, Nb, Ta, and C were optimized to achieve better mechanical properties at high temperatures. Hence, workability of the alloy B and Gr.92 were compared. An increase in the B content affected the phase transformation temperature and texture of the steel. The development of the {111}<uvw> components in γ-fibers depended on the austenite fraction of the steel after the phase transformation. An increase in the B content of the steel increased its α-to-γ phase transformation temperature, thus preventing the occurrence of sufficient transformation under the normalizing condition. Cracks occurred at the point of the elastic-to-plastic deformation transition in the normal direction during the rolling process, thereby resulting in failure. Therefore, it is necessary to avoid intermediate heat treatment conditions, in which γ-fibers do not fully develop, i.e., to avoid an imperfect normalization.

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Section: Introductionmentioning

confidence: 99%

Influence of Heat Treatment on the Workability of Modified 9Cr-2W Steel with Higher B Content

Heo

Kim

et al. 2019

Metals

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“…Ferritic-martensitic (FM) steels have been considered as fuel cladding and duct materials for a SFR owing to their high thermal conductivities, low expansion coefficients and superior irradiation swelling compared to austenitic steel [8][9][10]. However, the creep rupture strength of FM steels abruptly decreases during long term creep exposure at high temperature [11].…”

Section: Introductionmentioning

confidence: 99%

“…Nuclear fuel cladding tube which transfers efficient the fission energy and confines nuclear fuel rod and fissile material is a main component. Hence, the development of fuel cladding tube is essential as it is the most important component directly related to the safety of nuclear reactor.Ferritic-martensitic (FM) steels have been considered as fuel cladding and duct materials for a SFR owing to their high thermal conductivities, low expansion coefficients and superior irradiation swelling compared to austenitic steel [8][9][10]. However, the creep rupture strength of FM steels abruptly decreases during long term creep exposure at high temperature [11].…”

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Influence of Heat Treatment on the Workability of Modified 9Cr-2W Steel with Higher B Content

Heo¹,

Kim²,

Kim³

et al. 2019

Preprint

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In this study, the effect of heat treatment was investigated to influence the occurrence of fracture during manufacturing process of Alloy B steel with boron contents as high as 130 ppm. As the content of boron increases, it affects the phase transformation temperature and texture. The development of {111} components in the γ-fiber is affected depending on the austenite fraction after phase transformation. The Alloy B steel indicated that the increase in the boron content increased the α to γ phase transformation temperature such that sufficient transformation did not occur in the normalizing condition. The cracks occurred at the point of the transition from elastic to plastic deformation in the ND direction during the rolling process, thereby resulting in failure.Therefore, it is necessary to avoid the intermediate heat treatment condition in which γ-fiber does not fully develop, i.e., an imperfect normalization. IntroductionNuclear power generation plays a key role in the Korea energy with low costs of raw materials and excellent base load capacity, however its enlargement is limited due to problem of spent nuclear fuel after operation. To solve these problems, it is necessary to develop an innovative nuclear power plant which can contribute to sustainable development, environmental protection and preparation for rapidly increasing energy consumption [1,2].Recently, research has carried out to develop sodium cooled fast reactor (SFR) because it has many advantages in terms of economic efficiency, stability, nuclear non-proliferation and reducing the emission of spent nuclear fuel. It is designed to operate at temperature much higher than those in light water reactors and to improve thermal efficiency [3][4][5][6][7]. Nuclear fuel cladding tube which transfers efficient the fission energy and confines nuclear fuel rod and fissile material is a main component. Hence, the development of fuel cladding tube is essential as it is the most important component directly related to the safety of nuclear reactor.Ferritic-martensitic (FM) steels have been considered as fuel cladding and duct materials for a SFR owing to their high thermal conductivities, low expansion coefficients and superior irradiation swelling compared to austenitic steel [8][9][10]. However, the creep rupture strength of FM steels abruptly decreases during long term creep exposure at high temperature [11]. An advanced FM steel alloy was developed on the basis of Gr.92 steel. Minor alloying elements such as B, N, Nb, Ta, and C Preprints (www.preprints.org) | NOT PEER-REVIEWED | Posted: 16

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“…In particular, it is shown from the operational experience records for the PHENIX, BN-600, and FBTR that SFRs are sufficiently reliable to be operated up to a comparable availability level of LWRs [10]. In addition, SFRs have more than 300 reactor years of practical operation and there have been active research projects for the design and construction of advanced SFRs such as ASTRID in France [11] and PGSFR [12] in South Korea. The sodium-cooled fast reactors for burning TRUs from PWR spent fuels are designed to have a low conversion ratio by reducing fuel volume fraction or reducing neutron leakage or increasing neutron absorption such that a large amount of external TRUs from PWR spent fuel stocks are steadily fed into them and consumed by neutron reactions.…”

Section: Introductionmentioning

confidence: 99%

An Advanced Sodium-Cooled Fast Reactor Core Concept Using Uranium-Free Metallic Fuels for Maximizing TRU Burning Rate

You

2017

Sustainability

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Abstract:In this paper, we designed and analyzed advanced sodium-cooled fast reactor cores using uranium-free metallic fuels for maximizing burning rate of transuranics (TRU) nuclides from PWR spent fuels. It is well known that the removal of fertile nuclides such as 238 U from fuels in liquid metal cooled fast reactor leads to the degradation of important safety parameters such as the Doppler coefficient, coolant void worth, and delayed neutron fraction. To resolve the degradation of the Doppler coefficient, we considered adding resonant nuclides to the uranium-free metallic fuels. The analysis results showed that the cores using uranium-free fuels loaded with tungsten instead of uranium have a significantly lower burnup reactivity swing and more negative Doppler coefficients than the core using uranium-free fuels without resonant nuclides. In addition, we considered the use of axially central B 4 C absorber region and moderator rods to further improve safety parameters such as sodium void worth, burnup reactivity swing, and the Doppler coefficient. The results of the analysis showed that the final design core can consume~353 kg per cycle and satisfies self-controllability under unprotected accidents. The fuel cycle analysis showed that the PWR-SFR coupling fuel cycle option drastically reduces the amount of waste going to repository and the SFR burner can consume the amount of TRUs discharged from 3.72 PWRs generating the same electricity.

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Metal Fuel Development and Verification for Prototype Generation IV Sodium-Cooled Fast Reactor

Cited by 28 publications

References 18 publications

Influence of Heat Treatment on the Workability of Modified 9Cr-2W Steel with Higher B Content

Influence of Heat Treatment on the Workability of Modified 9Cr-2W Steel with Higher B Content

Influence of Heat Treatment on the Workability of Modified 9Cr-2W Steel with Higher B Content

An Advanced Sodium-Cooled Fast Reactor Core Concept Using Uranium-Free Metallic Fuels for Maximizing TRU Burning Rate

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