NUCLEAR TECHNIQUES, Volume. 47, Issue 8, 080605(2024)
Preliminary analysis of nuclear criticality safety of micro-reactor under high-speed impact
Fig. 2. Geometric diagram of pure fuel reactor vertical impact with ground
Fig. 3. Yield surface of constitutive model of crushed foam model[15]
Fig. 4. Geometric diagram of cylinder reactor impact the ground at a 30° angle
Fig. 5. Density change in fuel vertical impact with ground (a) 0 s, (b) 0.001 05 s, (c) 0.001 2 s, (d) 0.001 5 s
Fig. 6. Normalized neutron flux change in fuel vertical impact with ground (a) 0 s, (b) 0.001 05 s, (c) 0.001 2 s, (d) 0.001 5 s
Fig. 7. Normalized heating change in fuel vertical impact with ground (a) 0 s, (b) 0.001 05 s, (c) 0.001 2 s, (d) 0.001 5 s
Fig. 8. Strain pressure change in fuel vertical impact with ground (a) 0 s, (b) 0.001 05 s, (c) 0.001 2 s, (d) 0.001 5 s
Fig. 9. Discrepancies in keff values for different codes under uniform density variation
Fig. 10. Criticality properties of fuel vertical impact with ground at different times
Fig. 11. Percentage difference in flux and heating distribution between uniform (a) and nonuniform (b) densities
Fig. 12. Density change in cylinder reactor under 30° impact with ground (a) 0 s, (b) 0.001 05 s, (c) 0.002 4 s, (d) 0.003 s
Fig. 13. Normalized thermal neutron flux change in cylinder reactor under 30° impact with ground(a) 0 s, (b) 0.001 05 s, (c) 0.002 4 s, (d) 0.003 s
Fig. 14. Normalized heating change in cylinder reactor 30° impact with ground (a) 0 s, (b) 0.001 05 s, (c) 0.002 4 s, (d) 0.003 s
Fig. 15. Strain pressure change in cylinder reactor under 30° impact with ground (a) 0 s, (b) 0.001 05 s, (c) 0.002 4 s, (d) 0.003 s
Fig. 16. Discrepancies in keff values for different codes under uniform density variation
Fig. 17. Criticality properties of cylinder reactor under 30° impact with ground at different times
Fig. 18. Difference in thermal neutron flux and heating distribution between uniform (a) and nonuniform density (b) of cylinder core
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Lipeng WANG, Lu CAO, Lixin CHEN, Rui LI, Shichang LIU, Da LI, Xinyi ZHANG, Duoyu JIANG, Tianliang HU, Xinbiao JIANG. Preliminary analysis of nuclear criticality safety of micro-reactor under high-speed impact[J]. NUCLEAR TECHNIQUES, 2024, 47(8): 080605
Category: NUCLEAR ENERGY SCIENCE AND ENGINEERING
Received: Sep. 14, 2023
Accepted: --
Published Online: Sep. 23, 2024
The Author Email: WANG Lipeng (wang0214@126.com)