Airtightness Test Technology for Reactor Compartment

Lin Xiaoling; Tian Yanjie

doi:10.13832/j.jnpe.2016.02.0129

Volume 37 Issue 2

Feb. 2025

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Lin Xiaoling, Tian Yanjie. Airtightness Test Technology for Reactor Compartment[J]. Nuclear Power Engineering, 2016, 37(2): 129-131. doi: 10.13832/j.jnpe.2016.02.0129

Citation:

Lin Xiaoling, Tian Yanjie. Airtightness Test Technology for Reactor Compartment[J]. Nuclear Power Engineering, 2016, 37(2): 129-131. doi: 10.13832/j.jnpe.2016.02.0129

Lin Xiaoling, Tian Yanjie. Airtightness Test Technology for Reactor Compartment[J]. Nuclear Power Engineering, 2016, 37(2): 129-131. doi: 10.13832/j.jnpe.2016.02.0129

Citation:

Lin Xiaoling, Tian Yanjie. Airtightness Test Technology for Reactor Compartment[J]. Nuclear Power Engineering, 2016, 37(2): 129-131. doi: 10.13832/j.jnpe.2016.02.0129

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Airtightness Test Technology for Reactor Compartment

doi: 10.13832/j.jnpe.2016.02.0129

Nuclear Safety and Chemical Defense Institute, Beijing, 100077, China

Received Date: 2015-05-28
Rev Recd Date: 2015-10-08

Available Online: 2025-02-15

Abstract

Abstract

Two different methods to test the reactor compartment airtightness have been set up, which are the pressure reduction and the indicator leakage. Measurement and analysis ways in the two methods have been separately presented according to their principle bases. Based on the theory analysis, SF₆ has been verified to act as the indicator in the indicator leakage test.
- Reactor compartment,
- Airtightness,
- Test