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부지환경종합관리시스뎀 개발용 SEMS모듈 설계에 관한 연구
고도영,박세문,김창락,Ko Do-Young,Park Se-Moon,Kim Chang-Lak 한국방사성폐기물학회 2004 방사성폐기물학회지 Vol.2 No.4
During the last two years, Site Information and Total Environmental database management System (SITES) ver. 1.0 has been developed for the systematic SITES Database Module (SDM), which includes site information, facility information and environmental information. The SITES includes the module for site environmental monitoring system and safety assessment (M&A) system for the nuclear facility. SITES is expected to be an effective system for the radioactive waste disposal management facility. Currently, SITES ver.2.0 is under development after the SITES ver.1.0 that is focused on the M&A system. The main purpose of this paper is to introduce and try to account for the major development in the concept of SEMS sub-module of the M&A module. The SEMS is purposed of development of the program for real time environmental monitoring, prediction, and automatic alarm system using SITES Database and related information.
APR1400 원자로 축소모델 구조해석을 위한 상관길이
고도영(Do-young Ko),김규형(Kyu-hyung Kim),장호철(Ho-cheol Jang) 한국소음진동공학회 2023 한국소음진동공학회 논문집 Vol.33 No.2
The correlation length for structural analysis can be calculated by installing several dynamic pressure transducers and evaluating the measured values in scale model testing. This study was conducted under the normal operating condition of the reactor in KHNP-STAR, which was designed and manufactured as a 1/7 scale-down model for APR1400. To verify conservative design at APR1400 reactor internals, the correlation length was evaluated at two locations: (1) the downcomer of the reactor coolant, and (2) the control element assembly guide tube. The correlation length calculated in this study will be used for the structural analysis aspect in the scale model testing of the APR1400 reactor internals.
APR1400 원자로내부구조물 종합진동평가 측정위치 선정기준 개발
고도영(Do-Young Ko),김규형(Kyu-Hyung Kim),김성환(Sung-Hwan Kim) 한국소음진동공학회 2011 한국소음진동공학회 학술대회논문집 Vol.2011 No.4
A basic concept for selection criteria of measuring places of RVI CVAP is to determine measuring places and sensors based on the results of the hydraulic and structural analysis for RVI CVAP in APR1400. In addition, there is the important selection criteria to determine measuring places for measurement of RVI CVAP ; the first is to choose measuring places according to U.S. NRC R.G. 1.20, the second is to select measuring places by RVI design review, the third is to option on the basis of measurement results of SYSTEM 80, the forth is to decide using review results on a design change of a reactor and the last is to determine using the review on the possibility of installation/removal of sensors and structures for the measurement. We developed selection criteria of measuring places for RVI CVAP in APR1400 and this will be directly applied to the measurement program for RVI CVAP.
APR1400 원자로 내부구조물 종합진동평가 측정센서 선정
고도영(Do-Young Ko),이재곤(Jae-Gon Lee) 한국소음진동공학회 2010 한국소음진동공학회 학술대회논문집 Vol.2010 No.10
Reactor vessel internals comprehensive vibration assessment program(RVI CVAP) is one of the necessary tests to ensure the safety of nuclear power plants. RVI CVAP of U.S. Nuclear Regulatory Commission Regulatory Guide 1.20(U.S. NRC R.G. 1.20) consists of the analysis, measurement, and inspection. One of the core technologies of the measurement program for RVI CVAP is to select suitable sensors. We analyzed RVI design data of Palo Verde nuclear generating station(U.S.) and Yonggwang nuclear generating station(Korea) and investigated measuring sensors used in both of them; moreover, we investigated sensors used for measurement of RVI CVAP for the last 20 years throughout the world. Based on these results, we selected the most suitable sensors for RVI CVAP in Advanced Power Reactor 1400(APR1400).
논에서 가축분퇴·액비 사용에 따른 이앙기 배출수 양분부하량 특성
고도영 ( Do-young Ko ),안병구 ( Byung-koo Ahn ),김태복 ( Tae-bok Kim ),장영환 ( Young-hwan Jang ),장수연 ( Su-yeon Jang ),전형권 ( Hyong-gwon Chon ) 한국환경농학회 2019 한국환경농학회 학술대회집 Vol.2019 No.-
지속 가능한 농업생산 효율 및 환경 관리를 위해 농경지 수질환경을 평가하기 위하여 전북농업 기술원 원내 시험포장에서 2017년부터 2018년까지 벼를 재배하면서 배출수 양분 부하량을 조사하였다. 처리자재는 무기질비료, 가축분 분말·입상퇴비, 그리고 가축분뇨발효액(액비)을 시용하였다. 무기질비료와 액비는 이앙 3일전, 가축분 분상·입상퇴비는 이앙 25일전에 질소기준 9 kg/10a 수준이 되도록 무기질비료는 표준재배법에 따라 처리하였고, 액비와 가축분퇴비는 전량 밑거름으로 처리하였다. 처리 전 토양화학성은 pH 5.8, EC 0.30 dS/m, OM 53 g/kg, 유효인산 18.3 mg/kg, 유효규산 218 mg/kg 인 미사질양토이었다. 벼 품종은 신동진이었고, 재식밀도를 30 x 14 cm 간격으로 매년 6월 10일에 이앙하였다. 물 로타리를 한 후 이앙하기 위하여 배출한 유출수의 BOD 농도는 2년간 조사한 값의 평균은 1.90∼3.51 mg/L, COD는 13.17∼15.96 mg/L, T-N은 16.00∼16.94 mg/L, T-P는 0.25∼0.41 mg/L 범위로 각각 조사되었다. 이앙기 각 처리자재별 원단위 양분 배출농도를 비교하면 BOD와 COD는 액비처리구와 입상퇴비구가 분말퇴비구와 무기질 비료구보다 높았고, T-N은 분말퇴비구가 높았으며, T-P는 액비구가 높은 배출농도를 보였다. 이상의 결과에서 이앙기의 BOD는 액비 > 무기질비료 > 입상퇴비 > 분상퇴비 처리구 순이었고, T-N은 분말퇴비 > 액비 > 입상퇴비 > 무기질비료 순이었고, T-P는 액비 > 분말퇴비 > 무기질비료> 입상퇴비 순으로 조사되었다. 따라서 논에서 자원재활용 측면에서 가축분뇨발효액(액비)을 사용 할 수 있지만수질환경 측면에서는 사용량과 사용시기를 고려해야 할 필요가 있다.
고도영(Do-young Ko),이재곤(Jae-gon Lee),임재현(Jae-hyun Im),김만우(Man-woo Kim) 대한기계학회 2017 대한기계학회 춘추학술대회 Vol.2017 No.11
The Korean nuclear power plants (NPPs) have not used wireless technology because of potential possibilities related to the adverse impacts or unexpected shutdowns by electromagnetic and radio-frequency interference (EMI/RFI) and cyber security. This paper describes feasibility of wireless technology for equipment condition monitoring based on investigations of the Electric Power Research Institute (EPRI) technical reports, visiting of the thermal power plants in Korea and the nuclear power plants in the U.S, and the regulation requirements. We proposed that wireless equipment condition monitoring in the Korean nuclear power plants can be applied at all area and system also regulation requirements can be satisfied.
Comprehensive Vibration Assessment Program Measurement Test Plan for Advanced Power Reactor 1400
Do-Young Ko(고도영),Kyu-Hyung Kim(김규향) 한국소음진동공학회 2013 한국소음진동공학회 학술대회논문집 Vol.2013 No.4
미국 원자력규제위원회 규제지침(US NRC RG) 1.20의 비원형범주(non-prototype)-2를 기준으로 신형 경수로 1400(APR1400) 원자로내부구조물(RVI)의 설계수명기간 동안 건전성이 확보될 수 있는지를 확인하기 위해 종합진동평가프로그램(CVAP)을 수행하고 있다. US NRC RG 1.20의 비원형범주-2는 진동 및 응력 해석프로그램, 제한적 진동 측정프로그램, 검사프로그램 그리고 이런 프로그램들의 비교, 평가로 구성된다. 이 논문은 APR1400 RVI CVAP 측정프로그램의 측정계획, 시험, 허용기준과 결과 및 문서화에 대한 내용을 기술하였다. 우리는 이 논문의 진동측정 계획 및 시험에 따라서 APR1400 RVI CVAP 제한적 진동 측정프로그램을 수행할 것이다. A reactor vessel internals comprehensive vibration assessment program(RVI CVAP) of an advanced power reactor 1400(APR1400) is being verified on the integrity of RVI for the design life of the plant by performing the non-prototype category-2 type on the US Nuclear Regulatory Commission Guide(NRC RG) 1.20, for which consists of a vibration and stress analysis program, a limited vibration measurement program, an inspection program, and the correlation of these programs. The aim of this paper is to describe the plan for the vibration measurement, test and acceptance criteria portion, and documentation and results of the APR1400 RVI CVAP. We will conduct the limited vibration measurement program of the APR1400 RVI CVAP according to the measurement plan and the vibration measurement testing in this paper.