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

Kerntechnik ◽  
2021 ◽  
Vol 86 (1) ◽  
pp. 39-44
Author(s):  
K. Ryu ◽  
T. Lee ◽  
D. Baek ◽  
J. Park ◽  
N. Kim

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.

2016 ◽  
Vol 2 (2) ◽  
pp. 44
Author(s):  
Daniel Algernon ◽  
Sascha Feistkorn ◽  
Michael Scherrer

<p>Nondestructive Testing (NDT) is an important means to ensure structural integrity and safe operation of components in many industries, as for example nuclear power plants, aerospace or civil engineering. Within the qualification of Nondestructive Testing personnel as well as validation of NDT procedures, practical demonstrations on test blocks with realistic flaws play a key role. Adequate test pieces need to be designed according to specific criteria such as quantity, shape, orientation, size and position of the test flaws, depending on the requirements of the national codes and standards in the specific industries. The performance of the candidates and inspection systems is quantified and analyzed with respect to criteria, such as detection, positioning, characterization as well as length and height sizing of flaws. Statistic measures are applied to express the resulting accuracy and overall performance. The indication reports obtained from different candidates contain ample information, which might not appear evident at first sight. The complexity of the situation requires an intelligent extraction of the information from the data. An analysis tool <em>IndEva</em> was developed to handle this complexity and provide an accurate, detailed and reliable evaluation of inspection systems and personnel. Besides the plain evaluation regarding the fulfilment of the qualification requirements, critical test flaws as well as test block sections, which are likely to cause false positive indications can be identified. Statistic results display the dependency of the system performance on various parameters and parameter combinations to provide a clear picture of the performance. Country-specific evaluation standards can be applied and compared, especially with regard to the continuous improvement of the qualification methodology.</p>


2005 ◽  
Vol 297-300 ◽  
pp. 1418-1423 ◽  
Author(s):  
Chi Yong Park ◽  
Yong Sung Lee ◽  
Myung Hwan Boo

In steam generators of nuclear power plants, flow-induced vibration (FIV) can lead to tube damage by fretting-wear occurred due to impact and sliding movement between the tubes and their supports. There have been many studies and test results on wear damage of steam generator tubes but they were not reflected the mechanical and chemical conditions accurately. KEPRI nuclear power laboratory developed a wear test system, which is able to control the motion of impact and sliding simultaneously in the pressurized high temperature water-chemistry conditions. Some wear tests were performed to verify the stable operation for the wear test. This wear test system with new concepts was described briefly, and some data for verifying its performance have been shown in the cases of the selected some test results. In the test, Alloy 690 was used for tube materials and 409 stainless steel for support plates. A little data deviation was obtained and stability of system operation was investigated.


2003 ◽  
Vol 46 (4) ◽  
pp. 1464-1472 ◽  
Author(s):  
Young-Jin KIM ◽  
Jae-Boong CHOI ◽  
Joon-Seong LEE ◽  
Hyun-Kyu JUN ◽  
Youn-Won PARK

2013 ◽  
Vol 2 (1) ◽  
pp. 49-60 ◽  
Author(s):  
N. Gnanapragasam ◽  
D. Ryland ◽  
S. Suppiah

Subcritical water-cooled nuclear reactors (Sub-WCR) operate in several countries including Canada providing electricity to the civilian population. The high-temperature-steam-electrolysis process (HTSEP) is a feasible and laboratory-demonstrated large-scale hydrogen-production process. The thermal and electrical integration of the HTSEP with Sub-WCR-based nuclear-power plants (NPPs) is compared for best integration point, HTSEP operating condition and hydrogen production rate based on thermal energy efficiency. Analysis on integrated thermal efficiency suggests that the Sub-WCR NPP is ideal for hydrogen co-production with a combined efficiency of 36%. HTSEP operation analysis suggests that higher product hydrogen pressure reduces hydrogen and integrated efficiencies. The best integration point for the HTSEP with Sub-WCR NPP is upstream of the high-pressure turbine.


2014 ◽  
Vol 7 ◽  
pp. 457-468
Author(s):  
Arkadiy Zaryankin ◽  
Nikolay Rogalev ◽  
Galina Kurdiukova ◽  
Andrey Rogalev ◽  
Evgeny Lisin ◽  
...  

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