A study on accumulator analysis for the valve performance evaluation system of nuclear power plants

Author:

Ryu K.1,Lee T.1,Baek D.1,Park J.1,Kim N.2

Affiliation:

1. Korea Institute of Machinery and Materials 156 Gajeongbuk-Ro Yuseong-Gu Daejeon 34103 Korea Republic of Korea

2. Korea Atomic Energy Research Institute 111, Daedeok-daero 989 beon-gil, Yuseong-gu Daejeon , Republic of Korea

Abstract

Abstract To evaluate the valves used in the nuclear power plants are working properly under the required conditions, the performance and capacity test should be performed. In the test system, the accumulator was employed to control the large amount of high pressure and high temperature steam generated in the boiler precisely. In the accumulating process, the steam is often condensed. In order to prevent condensation, it is needed to install heaters and preheat the accumulator. However, if the size of the accumulator becomes large, the installation of the heater may not be easy. Therefore, when the test is conducted, the system was preheated by the latent heat generated from the phase change. Insufficient thermal insulation may cause temperature differences and it can cause mechanical problems in the accumulator structure. If insulation is sufficient, the temperature difference is indicated by the height. As the cooled condensate moves downwards, the condensate is discharged by the drain valve control and the temperature difference of the structure can be disappeared. The results of this paper can be applied to the conceptualization of equipment that uses latent heat and for the design of high-precision steam experimental devices or the design of high-capacity steam utilization systems.

Publisher

Walter de Gruyter GmbH

Subject

Safety, Risk, Reliability and Quality,General Materials Science,Nuclear Energy and Engineering,Nuclear and High Energy Physics,Radiation

Reference14 articles.

1. Korea Electric Association: Korea Electric Power Industry Code-Qualification of Active Valve Assemblies, Korea Electric Association, Seoul, 2010

2. American Society of Mechanical Engineers: Qualification of Active Mechanical Equipment Used in Nuclear Facilities, ASME, New York, 2007

3. Son, S.: Capacity certification status of pressure release device for nuclear power plant, Machinery and Materials 7 (2014) 50

4. Korea Electric Association: Korea Electric Power Industry Code-Pressure Relief Device Performance Test, Korea Electric Association, Seoul, 2010

5. American Society of Mechanical Engineers: Pressure Relief Devices, ASME, New York, 2008

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