Preliminary core design of the long life s-co2 Cooled fast reactor with 300wmth

Baolin Liu; Hongchun Wu; Youqi Zheng; Liangzhi Cao; Xianbao Yuan

doi:10.1115/ICONE22-30390

Preliminary core design of the long life s-co₂ Cooled fast reactor with 300wmth

Baolin Liu
, Hongchun Wu
, Youqi Zheng
, Liangzhi Cao
, Xianbao Yuan

School of Energy and Power Engineering

Xi'an Jiaotong University
China Three Gorges University

Research output: Chapter in Book/Report/Conference proceeding › Conference contribution › peer-review

Abstract

Gas cooled fast reactors are one of the Generation 4 nuclear power plants with hard neutron spectrum and high conversion ratio. In the study a long life Supercritical CO₂ (S-CO₂) cooled fast reactor core design with 300 MWth is presented. Physical calculation was carried out based on Dragon and CITATION, and thermal hydraulic analysis was performed based on the single channel code. The MOX fuel was utilized in the core design, and the tube-in-duct (TID) assembly was chosen for its excellent characteristics. According to the physical and thermal hydraulic coupling calculation, the reactor in the study can be operated with 300MWth for 20Ys without shuffling or refueling. Through the core life power peaking was kept relatively low, and the fuel temperature was kept below the 1800 degree centigrade.

Original language	English
Title of host publication	Next Generation Reactors and Advanced Reactors; Nuclear Safety and Security
Publisher	American Society of Mechanical Engineers (ASME)
ISBN (Electronic)	9780791845936
DOIs	https://doi.org/10.1115/ICONE22-30390
State	Published - 2014
Event	2014 22nd International Conference on Nuclear Engineering, ICONE 2014 - Prague, Czech Republic Duration: 7 Jul 2014 → 11 Jul 2014

Publication series

Name	International Conference on Nuclear Engineering, Proceedings, ICONE
Volume	3

Conference

Conference	2014 22nd International Conference on Nuclear Engineering, ICONE 2014
Country/Territory	Czech Republic
City	Prague
Period	7/07/14 → 11/07/14

Access to Document

10.1115/ICONE22-30390

Cite this

Liu, B., Wu, H., Zheng, Y., Cao, L., & Yuan, X. (2014). Preliminary core design of the long life s-co₂ Cooled fast reactor with 300wmth. In Next Generation Reactors and Advanced Reactors; Nuclear Safety and Security (International Conference on Nuclear Engineering, Proceedings, ICONE; Vol. 3). American Society of Mechanical Engineers (ASME). https://doi.org/10.1115/ICONE22-30390

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title = "Preliminary core design of the long life s-co2 Cooled fast reactor with 300wmth",

abstract = "Gas cooled fast reactors are one of the Generation 4 nuclear power plants with hard neutron spectrum and high conversion ratio. In the study a long life Supercritical CO2 (S-CO2) cooled fast reactor core design with 300 MWth is presented. Physical calculation was carried out based on Dragon and CITATION, and thermal hydraulic analysis was performed based on the single channel code. The MOX fuel was utilized in the core design, and the tube-in-duct (TID) assembly was chosen for its excellent characteristics. According to the physical and thermal hydraulic coupling calculation, the reactor in the study can be operated with 300MWth for 20Ys without shuffling or refueling. Through the core life power peaking was kept relatively low, and the fuel temperature was kept below the 1800 degree centigrade.",

author = "Baolin Liu and Hongchun Wu and Youqi Zheng and Liangzhi Cao and Xianbao Yuan",

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doi = "10.1115/ICONE22-30390",

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Liu, B, Wu, H, Zheng, Y, Cao, L & Yuan, X 2014, Preliminary core design of the long life s-co₂ Cooled fast reactor with 300wmth. in Next Generation Reactors and Advanced Reactors; Nuclear Safety and Security. International Conference on Nuclear Engineering, Proceedings, ICONE, vol. 3, American Society of Mechanical Engineers (ASME), 2014 22nd International Conference on Nuclear Engineering, ICONE 2014, Prague, Czech Republic, 7/07/14. https://doi.org/10.1115/ICONE22-30390

Preliminary core design of the long life s-co₂ Cooled fast reactor with 300wmth. / Liu, Baolin; Wu, Hongchun; Zheng, Youqi et al.
Next Generation Reactors and Advanced Reactors; Nuclear Safety and Security. American Society of Mechanical Engineers (ASME), 2014. (International Conference on Nuclear Engineering, Proceedings, ICONE; Vol. 3).

Research output: Chapter in Book/Report/Conference proceeding › Conference contribution › peer-review

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N2 - Gas cooled fast reactors are one of the Generation 4 nuclear power plants with hard neutron spectrum and high conversion ratio. In the study a long life Supercritical CO2 (S-CO2) cooled fast reactor core design with 300 MWth is presented. Physical calculation was carried out based on Dragon and CITATION, and thermal hydraulic analysis was performed based on the single channel code. The MOX fuel was utilized in the core design, and the tube-in-duct (TID) assembly was chosen for its excellent characteristics. According to the physical and thermal hydraulic coupling calculation, the reactor in the study can be operated with 300MWth for 20Ys without shuffling or refueling. Through the core life power peaking was kept relatively low, and the fuel temperature was kept below the 1800 degree centigrade.

AB - Gas cooled fast reactors are one of the Generation 4 nuclear power plants with hard neutron spectrum and high conversion ratio. In the study a long life Supercritical CO2 (S-CO2) cooled fast reactor core design with 300 MWth is presented. Physical calculation was carried out based on Dragon and CITATION, and thermal hydraulic analysis was performed based on the single channel code. The MOX fuel was utilized in the core design, and the tube-in-duct (TID) assembly was chosen for its excellent characteristics. According to the physical and thermal hydraulic coupling calculation, the reactor in the study can be operated with 300MWth for 20Ys without shuffling or refueling. Through the core life power peaking was kept relatively low, and the fuel temperature was kept below the 1800 degree centigrade.

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