Quantitative Study on 5% Damage Rate of Steam Generator Heat Transfer Tube in M310 Unit

He Feng; Zhu Jianping; Lu Yuechuan; Lu Xifeng; Wang Xinjun; Li Xiao

doi:10.13832/j.jnpe.2022.04.0191

Volume 43 Issue 4

Aug. 2022

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Article Navigation > Nuclear Power Engineering > 2022 > 43(4): 191-195

He Feng, Zhu Jianping, Lu Yuechuan, Lu Xifeng, Wang Xinjun, Li Xiao. Quantitative Study on 5% Damage Rate of Steam Generator Heat Transfer Tube in M310 Unit[J]. Nuclear Power Engineering, 2022, 43(4): 191-195. doi: 10.13832/j.jnpe.2022.04.0191

Citation:

He Feng, Zhu Jianping, Lu Yuechuan, Lu Xifeng, Wang Xinjun, Li Xiao. Quantitative Study on 5% Damage Rate of Steam Generator Heat Transfer Tube in M310 Unit[J]. Nuclear Power Engineering, 2022, 43(4): 191-195. doi: 10.13832/j.jnpe.2022.04.0191

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Quantitative Study on 5% Damage Rate of Steam Generator Heat Transfer Tube in M310 Unit

doi: 10.13832/j.jnpe.2022.04.0191

Science and Technology on Reactor System Design Technology Laboratory, Nuclear Power Institute of China, Chengdu, 610213, China

Received Date: 2021-05-19
Rev Recd Date: 2022-04-26
Publish Date: 2022-08-04

Abstract

Abstract

For M310 nuclear power unit, Part 3 ( Radiochemistry Code ) of the Technical Specification of Chemistry and Radiochemistry specifies that when “¹³³Xe>92500 MBq/t or ¹³³Xe>37000 MBq/t and ¹³¹I/¹³³I>1.5”, execute the command "if the damage rate of heat transfer tube of at least one steam generator (SG) exceeds 5%, reduce the load to NS/SG mode at the rate of 50 mw/min". However, in the actual operation process, since it is impossible to judge whether the damage rate of SG tube exceeds 5%, it is impossible to determine whether to execute the instruction of "reducing the load to NS/SG mode at a rate of 50 MW/min". Therefore, for M310 nuclear power unit, the operation instruction in the Radiochemistry Code is not operable. This paper investigates the relevant radiochemistry operation instructions at home and abroad, fully understands the meaning of "the damage rate of heat transfer tubes exceeds 5%”, and makes quantitative analysis. Through the analysis of the crack stability of the SG heat transfer tube under the leakage rate of 5, 24, 44 L/h, it is found that the unstable fracture of a single heat transfer tube will not occur at these leak rates, and then an operational suggestion is given: using the indicator "If the leak rate of at least one SG from the primary side to the secondary side exceeds 5 L/h" instead of the unquantifiable "If the damage rate of at least one SG heat transfer tube exceeds 5%", the safety and economy of nuclear power plant operation can be ensured.
- M310 unit,
- Heat transfer tube,
- Damage rate,
- Leak rate,
- Through-wall crack

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References(11)

References

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