Researching | Preliminary design of SiC composite cladding fuel rod with lead-bismuth eutectic filled pellet-cladding gap

Journals >NUCLEAR TECHNIQUES >Volume 48 >Issue 2 >Page 020604 > Article

NUCLEAR TECHNIQUES
Vol. 48, Issue 2, 020604 (2025)

Preliminary design of SiC composite cladding fuel rod with lead-bismuth eutectic filled pellet-cladding gap

Ruixiao ZHANG, Yanan HE, Jing ZHANG^*, Yingwei WU..., Wenxi TIAN, Suizheng QIU and Guanghui SU|Show fewer author(s)

Author Affiliations

School of Nuclear Science and Technology, Xi'an Jiaotong University, Xi'an 710049, China

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DOI: 10.11889/j.0253-3219.2025.hjs.48.230206 Cite this Article

Ruixiao ZHANG, Yanan HE, Jing ZHANG, Yingwei WU, Wenxi TIAN, Suizheng QIU, Guanghui SU. Preliminary design of SiC composite cladding fuel rod with lead-bismuth eutectic filled pellet-cladding gap[J]. NUCLEAR TECHNIQUES, 2025, 48(2): 020604 Copy Citation Text

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References

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[3] Snead L L, Nozawa T, Katoh Y et al. Handbook of SiC properties for fuel performance modeling[J]. Journal of Nuclear Materials, 371, 329-377(2007).

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[7] DENG Yangbin, HE Yanan, WU Yingwei et al. Multi-layer clad and non-rigid pellet mechanical modeling and its application[J]. Atomic Energy Science and Technology, 52, 1308-1315(2018).

[8] He Y N, Shirvan K, Wu Y W et al. Fuel performance optimization of U3Si2-SiC design during normal, power ramp and RIA conditions[J]. Nuclear Engineering and Design, 353, 110276(2019).

[9] He Y N, Chen P, Wu Y W et al. Preliminary evaluation of U3Si2-FeCrAl fuel performance in light water reactors through a multi-physics coupled way[J]. Nuclear Engineering and Design, 328, 27-35(2018).

[10] Chen P, Qiu B W, Li Y M et al. An evaluation on in-pile behaviors of SiCf/SiC cladding under normal and accident conditions with updated FROBA-ATF code[J]. Nuclear Engineering and Technology, 53, 1236-1249(2021).

[11] Katoh Y, Snead L L. Silicon carbide and its composites for nuclear applications–Historical overview[J]. Journal of Nuclear Materials, 526, 151849(2019).

[12] Sukjai Y. Silicon carbide performance as cladding for advanced uranium and thorium fuels for light water reactors[D](2014).

[13] Terrani K, Balooch M, Carpenter D et al. Irradiation effects on thermal properties of LWR hydride fuel[J]. Journal of Nuclear Materials, 486, 381-390(2017).

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[15] Deng Y B, Shirvan K, Wu Y W et al. Probabilistic view of SiC/SiC composite cladding failure based on full core thermo-mechanical response[J]. Journal of Nuclear Materials, 507, 24-37(2018).

[16] Shapovalov K, Jacobsen G M, Alva L et al. Strength of SiCf-SiCm composite tube under uniaxial and multiaxial loading[J]. Journal of Nuclear Materials, 500, 280-294(2018).

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[19] Katoh Y, Snead L L, Nozawa T et al. Thermophysical and mechanical properties of near-stoichiometric fiber CVI SiC/SiC composites after neutron irradiation at elevated temperatures[J]. Journal of Nuclear Materials, 403, 48-61(2010).

[20] Katoh Y, Snead L L, Cheng T et al. Radiation-tolerant joining technologies for silicon carbide ceramics and composites[J]. Journal of Nuclear Materials, 448, 497-511(2014).

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Ruixiao ZHANG, Yanan HE, Jing ZHANG, Yingwei WU, Wenxi TIAN, Suizheng QIU, Guanghui SU. Preliminary design of SiC composite cladding fuel rod with lead-bismuth eutectic filled pellet-cladding gap[J]. NUCLEAR TECHNIQUES, 2025, 48(2): 020604

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