Preliminary application of neutronics calculation in LFR reactor with metallic fuel using dragon code

Zhang Liang; Sun Sheng; Sun Shouhua; Yang Wenhua

doi:10.11884/HPLPB202234.220001

Volume 34 Issue 5

Apr. 2022

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Zhang Liang, Sun Sheng, Sun Shouhua, et al. Preliminary application of neutronics calculation in LFR reactor with metallic fuel using dragon code[J]. High Power Laser and Particle Beams, 2022, 34: 056005. doi: 10.11884/HPLPB202234.220001

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Zhang Liang, Sun Sheng, Sun Shouhua, et al. Preliminary application of neutronics calculation in LFR reactor with metallic fuel using dragon code[J]. High Power Laser and Particle Beams, 2022, 34: 056005. doi: 10.11884/HPLPB202234.220001

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Preliminary application of neutronics calculation in LFR reactor with metallic fuel using dragon code

doi: 10.11884/HPLPB202234.220001

Reactor Operation and Application Sub-Institute, Nuclear Power Institute of China, Chengdu 610213, China

Received Date: 2022-01-04
Rev Recd Date: 2022-03-14

Available Online: 2022-03-19

Publish Date: 2022-05-15

Abstract

Abstract

Lead-bismuth/lead cooled fast reactor (LFR) is one of the fourth-generation advanced nuclear energy systems with good application prospects. Aiming at the application of two metallic fuels (UZr, UPuZr) with annular slug in an LFR fuel assembly and a typical LFR core, the Dragon/Donjon code was used to perform neutronics calculations. The results of 172-group and 295-group neutron databases based on the ENDF/B 8.0 library and the transport method (SP3) and the diffusion method (MCFD) were obtained and compared with the results using RMC code. The k_eff deviations using SP3 algorithm for UZr fuel are less than 550×10⁻⁵, and for UPuZr fuel, the k_eff deviations obtained by MCFD algorithm are less than −700×10⁻⁵. The maximum deviation of control rod worth is 7.6%, and the results using 172-grouplib and 295-grouplib are basically the same. By using the SP3 algorithm, the fuel assembly power deviations are less than ±6.0%, and the deviation with the SP3 algorithm is less than that with MCFD algorithm. The results preliminarily prove the feasibility of the Dragon/Donjon code for reactor physics analysis of LFR with metallic fuel.
- lead bismuth cooled fast reactor,
- metallic fuel,
- reactor physics,
- Dragon/Donjon code

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References(20)

References

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