NUCLEAR TECHNIQUES, Volume. 46, Issue 11, 110602(2023)
Analysis of typical flow blockage accidents of single annular fuel assembly for lead-bismuth cooled fast reactor
Fig. 4. Mesh sensitivity analysis (a) Subchannel 49, (b) Subchannel 21
Fig. 6. Effect of blockage area on axial cladding temperature (a) Inner channel, (b) Outer channel
Fig. 7. Distribution of axial velocity field around blockage of case B2, B3, B4
Fig. 8. Radial temperature distribution at blockage (a) Inner channel, (b) Outer channel
Fig. 9. Effect of blockage thickness on axial cladding temperature (a) 25% blockage of inner channel, (b) 25% blockage of outer channel, (c) 75% blockage of inner channel, (d) 75% blockage of outer channel
Fig. 10. Distribution of axial velocity field around blockage of case A2, A4
Fig. 11. Radial temperature distribution at blockage (a) 25% blockage of inner channel, (b) 25% blockage of outer channel, (c) 75% blockage of inner channel, (d) 75% blockage of outer channel
Fig. 12. Effect of axial position of the blockage on axial cladding temperature (a) Inner channel, (b) Outer channel
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Qi CHEN, Yufan LING, Pengcheng ZHAO, Yanan ZHAO, Tao YU. Analysis of typical flow blockage accidents of single annular fuel assembly for lead-bismuth cooled fast reactor[J]. NUCLEAR TECHNIQUES, 2023, 46(11): 110602
Category: Research Articles
Received: Jun. 18, 2022
Accepted: --
Published Online: Dec. 23, 2023
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