scholarly journals PRTR CONTAINMENT VESSEL LEAK RATE TEST EXPERIENCE.

1967 ◽  
Author(s):  
D.W. Hayes
Keyword(s):  
Leak Rate ◽  
Containment Vessel ◽  
Rate Test

scholarly journals Comparison of Measured and Calculated Data for NPP Krško CILR Test

Energies ◽  
2019 ◽  
Vol 12 (11) ◽  
pp. 2176
Author(s):  
Štefica Vlahović ◽  
Siniša Šadek ◽  
Davor Grgić ◽  
Tomislav Fancev ◽  
Vesna Benčik
Keyword(s):  
Nuclear Power ◽  
Calculated Data ◽  
Leakage Rate ◽  
Leak Rate ◽  
Measured Temperature ◽  
Test Results ◽  
Test Scenario ◽  
Weighting Factors ◽  
Containment Model ◽  
Rate Test

Containment is the last barrier for release of radioactive materials in the case of an accident in the nuclear power plant (NPP). Its overall integrity is tested during a containment integrated leak rate test (CILRT) at the design pressure, at regular intervals. Due to applied risk based licensing, the test intervals can be increased up to once in 10 years and beyond. Taking that into account it is important to prepare the test properly and to use obtained results to assess the real status of the containment. The test can be used to verify existing containment calculation models. There is a potential benefit of verified computer models usage for the explanation of some test results, too. NPP Krško has performed CILRT during the plant outage in 2016. The paper presents a comparison between measured data and results calculated using a multivolume GOTHIC (Generation Of Thermal Hydraulic Information For Containment) model. The test scenario was reproduced using limited available data up to the end of the pressurization phase. The depressurization phase is calculated by the code and measured leakage rate is implemented in the model. Taking into account the necessary adjustments in the model, overall prediction of the measured results (in terms of pressure, temperature and humidity) is very good. In the last phase of the test some non-physical behavior is noticed (without influence on overall test results), probably caused by the combination of air redistribution within the containment and influence of heat transfer to plant systems that were in the operation during the test. GOTHIC model was used to check sensitivity of the predicted pressure (leak rate) to different heat inputs and to investigate the influence that operation of only one reactor containment fan cooler (RCFC) train during pressurization can have on the mixing of air within the containment. In addition, the influence of currently used weighting factors (weighting of measured temperature, relative humidity and pressure data) on the used test methodology is investigated. The possible non-conservative direction of the influence (currently used weighting factors are giving lower leakage rate) was demonstrated and a new set of weighting factors is proposed too.

Leak rate test of personnel airlock for LWR containment subject to pressures and temperatures beyond design

1991 ◽  
Vol 125 (1) ◽  
pp. 23-40
Author(s):  
James T. Julien ◽  
Steven W. Peters ◽  
D.B. Clauss
Keyword(s):  
Leak Rate ◽  
Rate Test

Structural Integrity Test of Steel Containment Vessel at the First AP1000 Unit of China

2017 ◽  
Author(s):  
Li Kai ◽  
Zhong Zhimin ◽  
Ma Xianhong
Keyword(s):  
Structural Integrity ◽  
Lessons Learned ◽  
Testing System ◽  
Integrity Test ◽  
Paper Briefly ◽  
Containment Vessel ◽  
Test Pressure ◽  
Rate Test ◽  
Design Requirements ◽  
Visual Testing

This paper briefly introduces the design functions, structure of steel containment vessel (CV) of AP1000 unit and its related design, fabrication, examination, and testing codes and standards. It focuses on the practices of Structural Integrity Test (SIT), of CV in Sanmen unit 1, which is the first steel CV in China. Its SIT aim and testing process, including pretest, baseline measurements, pressurization and depressurization process, displacements and strains measurement method and measurement point positions, Visual Testing and Leakage examination activities are discussed in detail. Some important feed backs or lessons learned from this testing also are discussed. The CV SIT results of Sanmen Unit 1 showed that the containment vessel behaved elastically and no cracks and leakage were observed during the test. After the containment vessel SIT, the Integrated Leak Rate Test ( ILRT ) was successfully completed. Therefore, it was confirmed that the tested CV had adequate structural integrity against the test pressure, its leak tight boundary met the design requirements, the testing system work well and the testing activities and its organization were successful.

Applicability of the Alternative Reagents to CFC112 for the Leak Rate Test of Iodine Removal Filters in PWR Nuclear Power Plants

2012 ◽  
Vol 38 (6) ◽  
pp. 372-377
Author(s):  
Norihisa Mori ◽  
Naoyuki Kamishima ◽  
Shoji Okamoto ◽  
Hiroshi Shiwaya
Keyword(s):  
Nuclear Power ◽  
Power Plants ◽  
Nuclear Power Plants ◽  
Leak Rate ◽  
Rate Test
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