In-core fuel management strategy design of lead-cooled fast reactor M<sup>2</sup>LFR-1000

Fang Haitao; Zhao Yongsong; Zhang Xilin; Zhou Xingbin; Li Wei; Chen Hongli

doi:10.11884/HPLPB201830.180083

Volume 30 Issue 9

Sep. 2018

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Fang Haitao, Zhao Yongsong, Zhang Xilin, et al. In-core fuel management strategy design of lead-cooled fast reactor M2LFR-1000[J]. High Power Laser and Particle Beams, 2018, 30: 096003. doi: 10.11884/HPLPB201830.180083

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Fang Haitao, Zhao Yongsong, Zhang Xilin, et al. In-core fuel management strategy design of lead-cooled fast reactor M²LFR-1000[J]. High Power Laser and Particle Beams, 2018, 30: 096003. doi: 10.11884/HPLPB201830.180083

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In-core fuel management strategy design of lead-cooled fast reactor M²LFR-1000

doi: 10.11884/HPLPB201830.180083

School of Physical Sciences, University of Science and Technology of China, Hefei 230027, China

Received Date: 2018-03-22
Rev Recd Date: 2018-05-10
Publish Date: 2018-09-15

Abstract

Abstract

Fuel management is an extremely important and complex work in reactor design and directly affects the economics of the reactor. Now, there are many mature fuel management calculation methods for PWR and other traditional thermal reactors around the world. However, because of their hard neutron spectra, control modes and power distributions of fast reactors are different from those of traditional thermal reactors. There is a lack of systematic study of fuel management for fast reactors. Based on the SRAC/COREBN software package which provides the atom density of the nuclides at different burnup levels, a pseudo-equilibrium cycle parameter was calculated for the fuel management pre-estimation of forced circulation lead cooled fast reactor M²LFR-1000 independently developed by University of Science and Technology of China. Then, refueling schemes of the initial, transition and equilibrium cycles were designed. The results show that optimizing the Pu enrichment of outer fuel assemblies in M²LFR-1000 core can extend the cycle length to 540 d and increase the average discharge burnup. The pseudo-equilibrium cycle results are basically the same as those of the equilibrium cycle. The pseudo-equilibrium cycle can be used for fuel management pre-estimation.
- lead-cooled fast reactor,
- fuel management,
- pseudo-equilibrium cycle,
- equilibrium cycle

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References(18)

References

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