scholarly journals Study on Performance Demonstration Test Result of Ultrasonic Examination in Nuclear Power Plant

2014 ◽  
Vol 34 (5) ◽  
pp. 384-389 ◽  
Author(s):  
Nam-Du Jung ◽  
Yong-Sig Moon ◽  
Seung-Pyo Lee
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Nuclear Power ◽  
Ultrasonic Examination ◽  
Performance Demonstration ◽  
Test Result

Implementation Status of Performance Demonstration for Nuclear Power Plant Piping Weld Ultrasonic Examination in Korea

2008 ◽  
Vol 580-582 ◽  
pp. 135-138
Author(s):  
Yong Sik Kim ◽  
Hee Jong Lee ◽  
Se Kyoung Kim
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Nuclear Power ◽  
Power Plants ◽  
Reactor Power ◽  
Ultrasonic Examination ◽  
Asme Code ◽  
Heavy Water Reactor ◽  
Implementation Status ◽  
Performance Demonstration

The ASME B&PV code section XI adopted the performance demonstration requirements (Appendix VIII) for the ultrasonic examination of nuclear power plant piping weld in the 1989 winter addenda for the first time. Korea Electric Power Research Institute(KEPRI) and Korea Hydro and Nuclear Power Company(KHNP) finished developing Korean Performance Demonstration(KPD) system for the ultrasonic examination to apply pressurized light-water and pressurized heavy-water reactor power plants piping weld in accordance with ASME code section XI, appendix VIII on January 2004. KEPRI has been accomplishing the performance demonstration for nuclear power plant piping weld ultrasonic examination in Korea from April 2004. This paper describes the implementation status of the performance demonstration for nuclear power plant piping weld ultrasonic examination in Korea.

Localization Prototype Research of RCC-M Ejector in Nuclear Power Plant

2013 ◽  
Vol 421 ◽  
pp. 181-185
Author(s):  
Yan Li Qi ◽  
Yuan Xue ◽  
Tian Tian ◽  
Xing Jiang Chen ◽  
Xi Quan Fang
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Nuclear Power ◽  
Stable Operation ◽  
Special Configuration ◽  
Safety Level ◽  
Practical Applications ◽  
Spray System ◽  
Nuclear Plants ◽  
Test Result

As the key equipment to ensure the stable operation of containment spray system in nuclear power plant, a RCC-M ejector with safe and credible performance is very important to make sure the containment integrality under lose of coolant accident (LOCA) or pipe broken. However, it was purchased from overseas supplier all along because of its special configuration, nonstandard design, severe safety level and small quantity demand. To implement equipment localization, and referring to practical applications of some nuclear plants, a RCC-M ejector is independently manufactured and tested, all performance could meet the requirement according to the test result. The RCC-M ejector is authenticated by experts by China Nuclear Energy Association, and the localization prototype research of this paper has great application and popularization value.

Seismic Test Result of Motor-Operated Butterfly Valve Actuators for Nuclear Power Plant

2018 ◽  
Author(s):  
Nobuo Kojima ◽  
Yoshitaka Tsutsumi ◽  
Kazuyoshi Yonekura ◽  
Koji Nishino ◽  
Yukio Watanabe ◽  
...  
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Nuclear Power ◽  
Earthquake Resistance ◽  
Test Results ◽  
Butterfly Valve ◽  
Resistance Evaluation ◽  
Vibration Tests ◽  
Seismic Tests ◽  
Test Result

Seismic tests were carried out to confirm the operability limit acceleration for a standard motor-operated butterfly valve actuator in three excitation directions. Based on the results, seismic brackets that can operate valves even in three directions at 20 × 9.8 m/s2 or more were designed in three representative models. For the model subjected to the seismic test, we mounted the designed seismic bracket and confirmed the operability of the butterfly valve actuator by carrying out vibration tests in three directions at 20 × 9.8 m/s2. We used these results and previously reported motor-operated valve actuator seismic test results to creat a revision (draft) of the earthquake resistance evaluation methods.

Seismic Test Result of Air Operated Valve Actuators for Nuclear Power Plant (Air Operated Globe Valve (Diaphragm Type) and Air Operated Butterfly Valve (Lever Type) )

2021 ◽  
Author(s):  
Yoshitaka Tsutsumi ◽  
motoaki fuji ◽  
Yoshitsugu Nekomoto ◽  
Shigeki Suzuki ◽  
Yoshinao Matsubara ◽  
...  
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Nuclear Power ◽  
Butterfly Valve ◽  
Globe Valve ◽  
Test Result

Expanded Influence of UT Performance Demonstration and Fitness-for-Service Analysis in the Nuclear Power Industry

2011 ◽  
Author(s):  
Owen F. Hedden ◽  
C. David Cowfer
Keyword(s):  
Structural Analysis ◽  
Power Plant ◽  
Nuclear Power Plant ◽  
Pressure Vessel ◽  
Nuclear Power ◽  
Probability Of Detection ◽  
Nuclear Power Industry ◽  
Nondestructive Examination ◽  
Performance Demonstration ◽  
Plant Components

This paper addresses recent development and application of ASME Boiler and Pressure Vessel Code and Code Case requirements for weld nondestructive examination (NDE) and for fitness-for-service (FFS) structural analysis of the flaws thus discovered. A brief description of the basis for this development is included. Reviews are presented of additions to the literature addressing applications to nuclear power plant components. Issues regarding application of Code Cases 2235 and N-529 are presented. Concerns regarding the importance of reliable probability of detection (POD) data for different weld categories are addressed. Concerns with appropriate acceptance standards for flaws in different weld categories and materials are also addressed.

Qualification of Ultrasonic Examination for RPV Nozzle to Shell Welds of EPR Nuclear Power Plant

2017 ◽  
Author(s):  
WeiQiang Wang ◽  
Zhe Yu ◽  
Xin Ye ◽  
HuaiDong Chen ◽  
GuanBing Ma
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Pressure Vessel ◽  
Nuclear Power ◽  
Ultrasonic Inspection ◽  
Primary Circuit ◽  
Ultrasonic Examination ◽  
Under Construction ◽  
Technical Solutions ◽  
Service Inspection

European Pressurized Reactor (EPR) nuclear power plant is now under construction in China. One of the biggest changes in the EPR reactor pressure vessel (RPV) is the nozzle to shell welds are designed as “set-on” principle instead of “set-in” principle in the CPR1000 units. The nozzle to shell welds of the EPR pressure vessel must be inspected according to the RSE-M code. This is necessary in order to guarantee the integrity of the primary circuit. The In-Service Inspection (ISI) program of EPR nuclear power plant demands the automatic ultrasonic inspection of the nozzle to shell welds from nozzle inner surface. This paper presents the technical characteristics of the EPR reactor vessel, and analyzes the in-service examination requirements of nozzle to shell welds. Technical solutions have been designed to perform the examination of the component. The qualification process of the ultrasonic examination of the nozzle to shell welds is also presented.

Comparison between Conventional and Performance Demonstration UT Method by Round Robin Test

2006 ◽  
Vol 321-323 ◽  
pp. 1754-1757
Author(s):  
Yong Sik Kim ◽  
Seung Han Yang ◽  
Byung Sik Yoon ◽  
Hee Jong Lee
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Ultrasonic Testing ◽  
Nuclear Power ◽  
Round Robin ◽  
Round Robin Test ◽  
Examination Result ◽  
And Performance ◽  
Main Components ◽  
Performance Demonstration

The results of ultrasonic testing performed during in-service inspection period for main components of nuclear power plant are affected by the performance of each inspector. To enhance the inspection reliability, the more restrictive qualification is required. KEPRI established Korean performance demonstration (KPD) system for the ultrasonic testing personnel, equipment and procedure which applied to the piping examination of nuclear power plant. A round robin test was conducted to evaluate the reliability of examination result by comparing conventional (DAC) UT and performance demonstration (PD) UT method. Participants took detection/length sizing test and depth sizing test using DAC method and PD method. The results showed that the PD method was preciser and more accurate than the conventional DAC method in length and depth sizing regardless of field experience and PD qualification status.

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