• 제어로봇시스템학회:학술대회논문집
• /
• 제어로봇시스템학회 1997년도 한국자동제어학술회의논문집; 한국전력공사 서울연수원; 17-18 Oct. 1997
• /
• pp.1367-1370
• /
• 1997

This paper presents a vision algorithm for finding the centers of steam generator tubes using the generalized symmetry transform, which is used for ECT(Eddy Current Test) of steam generator tubes in nuclear power plants. The geometrical properties of the image representing steam generator tubes shows that they have amost circular or somewhat elliptic appearances and each tube has strong symmetry about its center. So we apply the generalized symmetry transform to finding centers of steam geneator tubes. But applying the generalized symmetry transform itself without any modification gives difficulties in obtaining the exact centers of steam generator tubes. But applying the generalized symmetry transform itself without any modification gives difficulties in obtaining the exact centers of tubes due to the shadow effect generated by the local light installed inside steam generator. Therefore we make the generalized symmetry transform modified, which uses a modified phase weight function in getting the symmetry magnitude in order to overcome the misleading effect by the local light. The experimental results indicate that the proposed vision algorithm efficiently recongnizes centers of steam generator tubes.

• 대한기계학회:학술대회논문집
• /
• 대한기계학회 2004년도 춘계학술대회
• /
• pp.2047-2052
• /
• 2004

Inconel-600 alloy has been used as steam generator tube material for current pressurized water reactors (PWRs). The long-term operation of steam generators showed that the use of this material induced localized corrosion damages and increased tube wear of steam generator. To protect these problems, steam generator tube material is being changed to Inconel-690 alloy. Based on the current trend, we have chosen Inconel 690 as the Advanced Power Reactor 1400 (APR1400) steam generator(SG) tube material and performed the design optimization of preventive measure against tube fretting wear for the APR1400 steam generator. In this paper, we examined the technical consideration in this modification : the selection of material, wear characteristics, effect of the Egg-crate Flow Distribution Plate installation, and effect analysis of vertical strip installation.

• 한국정밀공학회:학술대회논문집
• /
• 한국정밀공학회 2005년도 춘계학술대회 논문집
• /
• pp.796-805
• /
• 2005

The tilting pad journal bearings have been widely used to support high pressure/high rotating turbine rotors owing to their inherent dynamic stability characteristics. However, fatigue damages in the upper unloaded pads and the break of locking pins etc. by pad fluttering are continuously taken place in the actual steam turbines. The purpose of this paper is to develop a new bearing model that can prevent bearing problems effectively by pad fluttering in a tilting pad journal bearing. A new bearing model which has a wedged groove is suggested from the studies of fluttering mechanism performed by previously research works. The fluttering characteristics of the upper unloaded pad are studied experimentally in order to verify the reliability of a new bearing model. It can be known that the phenomenon of pad fluttering nearly does not occurred in the new bearing model under the various experimental conditions. And it is observed that any kinds of bearing failures by pad fluttering does not detect in the application of acture steam turbines.

• 대한기계학회:학술대회논문집
• /
• 대한기계학회 2003년도 춘계학술대회
• /
• pp.49-54
• /
• 2003

Most of the operating pressurized water reactors (PWRs)has chosen Inconel 600 as steam generator tubing. The long-term operation of steam generators showed that the use of this material induced localized corrosion damages. The current trend is using Inconel 690 as a tube material for the replacement steam generators. Based on the current trend, we have chosen Inconel 690 for the advanced Power Reactor 1400 (APR1400) steam generator tube material. In this paper, we examined the technical consideration in this modification: the effect of chemical composition, thermal conductivity, corrosion resistance and wear characteristics

• Nuclear Engineering and Technology
• /
• 제53권8호
• /
• pp.2753-2760
• /
• 2021

This paper proposes using sodium-cooled fast reactor technologies for use in hydrogen vapor methane (SMR) modification. Using three independent energy rings in the Russian BN-600 fast reactor, steam is generated in one of the steam-generating cycles with a pressure of 13.1 MPa and a temperature of 505 ℃. The reactor's second energy cycles can increase the gas-steam mixture's temperature to the required amount for efficient correction. The 620 ton/hr 540 ℃ steam generated in this cycle is sufficient to supply a high-temperature synthesis current source (700 ℃), which raises the steam-gas mixture's temperature in the reactor. The proposed technology provides a high rate of hydrogen production (approximately 144.5 ton/hr of standard H₂), also up to 25% of the original natural gas, in line with existing SMR technology for preparing and heating steam and gas mixtures will be saved. Also, exergy analysis results show that the plant's efficiency reaches 78.5% using HTR heat for combined hydrogen and power generation.

• 대한기계학회:학술대회논문집
• /
• 대한기계학회 2003년도 춘계학술대회
• /
• pp.1578-1583
• /
• 2003

LAVA-ERVC experiments have been performed to investigate the effect of insulation design features on the coolability in case of the external reactor vessel cooling (ERVC). All the 4 tests have been performed using Alumina iron thermite melt as a corium simulant. Due to the limited steam venting through the insulation, steam binding occurred inside the annulus in the KSNP case simulation. On the contrary, in the tests which were performed for simulating the APR1400 insulation design, sufficient water ingression and steam venting through the insulation lead to effective cool down of the vessel characterized by nucleate boiling. It could be found from the experimental results that modification of the insulation design allowing sufficient ventilation could increase the positive effects of the external reactor vessel cooling.

• 한국압력기기공학회 논문집
• /
• 제16권1호
• /
• pp.74-83
• /
• 2020

A number of so-called 'Type IV' cracking was reported to occur at the welded joints of the P91 steel or P92 steel reheat steam piping systems in Korean supercritical thermal power plants. The reheat steam piping systems are subjected to severe thermal and pressure loading conditions of coolant higher than 570℃ and 4MPa, respectively. In this study, piping analyses and design evaluations were conducted for the piping system of a specific thermal plant in Korea and suggestions were made how structural integrity could be improved so that type IV cracks at the welded joints could be prevented. Integrity evaluations were conducted as per ASME B31.1 code with implicit consideration of creep effects which was used in original design of the piping system and as per nuclear-grade RCC-MRx code with explicit consideration of creep effects. Comparisons were made between the evaluation results from the two design rules. Another approach with modification or reduction of the redundant supports in the piping systems was investigated as a tool to mitigate thermal stresses which should essentially contribute to prevention of Type IV cracking without major modification of the existing piping systems. In addition, a post weld heat treatment method and repair weld method which could improve integrity of the welded joint of P91 steel were investigated.

• Membrane and Water Treatment
• /
• 제8권4호
• /
• pp.355-367
• /
• 2017

In India, the current operation of condenser cooling system & effluent disposal system in existing power plants aims to reduce drawal of seawater and to achieve Zero Liquid Discharge to meet the demands of statutory requirements, water scarcity and ecological system. Particularly in the Steam-Electric power plants, condenser cooling system adopts Once through cooling (OTC) system which requires more drawal of seawater and effluent disposal system adopts sea outfall system which discharges hot water into sea. This paper presents an overview of closed-loop technology for condenser cooling system and to achieve Zero Liquid Discharge plant in Steam-Electric power plants making it lesser drawal of seawater and complete elimination of hot water discharges into sea. The closed-loop technology for condenser cooling system reduces the drawal of seawater by 92% and Zero Liquid Discharge plant eliminates the hot water discharges into sea by 100%. Further, the proposed modification generates revenue out of selling potable water and ZLD free flowing solids at INR 81,97,20,000 per annum (considering INR 60/Cu.m, 330 days/year and 90% availability) and INR 23,760 per annum (considering INR 100/Ton, 330 days/year and 90% availability) respectively. This proposed modification costs INR 870,00,00,000 with payback period of less than 11 years. The conventional technology can be replaced with this proposed technique in the existing and upcoming power plants.

• 과학교육연구지
• /
• 제42권2호
• /
• pp.132-147
• /
• 2018

본 연구에서는 과정중심 평가에 대한 이론적 모델을 STEAM 교육 맥락에서 핵심역량의 학습발달과정에 근거하여 개발, 제안하였다. 본 연구에서 제안하는 '과정-결과를 결합한 모듈 타입(Process-Products Combined Module-type)의 STEAM 평가모델(P2CM STEAM 평가모델)'은 문헌분석을 통해 도출된 것으로, STEAM 수업 맥락에서 핵심역량 학습발달과정에 초점을 둔 모델이다. 의 특징은 STEAM 수업과 평가를 연계하고, 과정평가와 결과평가가 동시에 가능하며, 다양한 STEAM 주제와 수업유형에 실제로 적용 가능한 점이다. 은 3개의 축으로 구성되는데, 첫 번째 축(X축)은 STEAM에서 중점을 두어야 할 4C 역량을, 두 번째 축(Y축)은 STEAM 수업유형의 종류와 위계를 나타내며, 세 번째 축은 학습발달 수준인 평가기준을 나타낸다. 에 기반으로 하여 창조기반의 창의역량에 초점을 둔 평가모듈(창의역량${\times}$창조기반)에서, 학생들의 학습발달과정을 평가할 수 있는 평가기준을 예시하였다. 연구결과를 토대로 한국형 LP에 대한 연구성과를 토대로 평가모델 개발하기, 현장밀착형 심층연구를 통한 증거기반 평가모델 개발 제공, 교사공동체 및 현장교사들의 참여를 통한 형성 평가 모델 수정보완, 학습발달수준 추적을 위한 평가모델에 대한 지속적인 연구의 필요성 등을 제안하였다.

• Korean Chemical Engineering Research
• /
• 제55권1호
• /
• pp.54-59
• /
• 2017

ABS 중합공정 중 잔류 모노머 회수 공정의 유틸리티 사용량 절감을 위한 공정의 개선을 수행하였다. ABS 폴리머 생산 과정 중 잔류 모노머 회수 공정은 제품의 품질 향상을 위해 반드시 필요하다. 잔류 모노머의 회수를 위한 다양한 방식이 있으나, 본 연구에서 대상으로 한 것은 스팀 스트리핑 공정이다. 기존의 스팀 스트리핑은 많은 양의 스팀과 냉각수가 사용되고 있으나, 본 연구를 통해 유틸리티 사용을 절감하는 새로운 방안을 찾고자 하였다. 스트리핑 후 모노머와 함께 배출되는 스팀의 잠열을 진공상태의 수증기로 회수하고, 압축으로 온도를 상승시켜 스트리핑 스팀으로 재사용하도록 함으로써 스팀의 사용을 획기적으로 절감하였다. 또한 모노머 최종 회수 과정에서 발생되는 물을 모노머 응축에 냉각수로 활용함으로써 용수에 대한 사용량도 감소 시킬 수 있었다.