원자력발전소의 디지털계측제어시스템의 사이버보안을 위한 디지털 자산분석 방법

구인수,김관웅,홍석붕,박근옥,박재윤,Koo, In-Soo,Kim, Kwan-Woong,Hong, Seok-Boong,Park, Geun-Ok,Park, Jae-Yoon 한국전자통신학회 2011 한국전자통신학회 논문지 Vol.6 No.6

원자력발전소의 계측제어계통은 제어, 감시기능을 수행하여 안전운전을 위한 두뇌 역할을 하는 핵심적인 분야이다. 최근 계측제어계통은 마이크로프로세서기반의 디지털 기술을 받아들여 디지털화되었다. 그러나 계측제어계통의 디지털시스템은 아날로그 기반 시스템에 비해 사이버위협에 매우 취약하여, 사이버공격에 의해 발전소 안전에 부정적인 영향을 받을 수 있다. 따라서 사이버침해에 대응할 수 있는 사이버 보안 대책이 계측제어계통에 요구된다. 사이버 보안성이 우수한 계통 설계를 위해서는 계측제어계통을 구성하는 자산에 대한 효과적인 자산분석이 요구된다. 본 연구에서는 원자로 계측제어설계의 사이버보안 적합성을 분석하기 위한 전 단계로 계측제어계통의 디지털 자산을 분석하기 위한 방법론을 제안한다. 제안된 디지털자산 분석 방법은 자산식별, 식별된 자산에 대한 평가방법으로 구성된다. 제안된 자산분석방법은 원자력발전소 계측제어계통의 사이버보안을 위한 자산분석에 응용하였다. Instrumentation & Control(I&C) System in NPP(Nuclear Power Plant) plays a important role as the brain of human being, it performs protecting, controling and monitoring safety operation of NPP. Recently, the I&C system is digitalized as digital technology such as PLC, DSP, FPGA. The different aspect of digital system which use digital communication to analog system is that it has potential vulnerability to cyber threat in nature. Possibility that digital I&C system is defected by cyber attack is increasing day by day. The result of cyber attack can be adverse effect to safety function in NPP. Therefore, I&C system required cyber security counter-measures that protect themselves from cyber threat efficiently and also cyber security design should be taken into consideration at concept stage in I&C system development process. In this study, we proposed the digital asset analysis method for cyber security assessment of I&C system design in NPP and we performed digital asset analysis of I&C system by using the proposed method.

고 선량율 감마선 조사에 따른 렌즈의 열화

조재완(Jai-Wan Cho),이준구(Joon-Koo Lee),허섭(Seop Hur),구인수(In-Soo Koo),홍석붕(Seok-Boong Hong) 대한전기학회 2009 전기학회논문지 Vol.58 No.7

Assumed that an IPTV camera system is to be used as an ad-hoc sensor for the surveillance and diagnostics of safety-critical equipments installed in the in-containment building of the nuclear power plant, an major problem is the presence of high dose-rate gamma irradiation fields inside the one. In order to uses an IPTV camera in such intense gamma radiation environment of the in-containment building, the radiation-weakened devices including a CCD imaging sensor, FPGA, ASIC and microprocessors are to be properly shielded from high dose-rate gamma radiation using the high-density material, lead or tungsten. But the passive elements such as mirror, lens and window, which are placed in the optical path of the CCD imaging sensor, are exposed to a high dose-rate gamma ray source directly. So, the gamma-ray irradiation characteristics of the passive elements, is needed to test. A CCD camera lens, made of glass material, have been gamma irradiated at the dose rate of 4.2 kGy/h during an hour up to a total dose of 4 kGy. The radiation induced color-center in the glass lens is observed. The degradation performance of the gamma irradiated lens is explained using an color component analysis.

뉴스초점 - 원자력 발전소 계측제어 시스템

구인수,Koo, In-Soo 한국기술사회 2010 技術士 Vol.43 No.2

At the end of last year, Korean nuclear power plants, APR-1400 and a research reactor have been contracted to build plants at United Arab Emirates and Jordan. Since 1959, a historical background of nuclear technologies in Korea is summarized. The safety requirements for Instrumentation and Control (I&C) systems in Nuclear Power Plants (NPP) are discussed. Specific descriptions on the typical safety classification of I&C systems, the definitions of the electrical class 1E and the countermeasures against common caused failures are provided. And summaries of typical I&C systems such as the protection systems, the control systems, the instrumentations, the monitoring systems and a control room in NPP are introduced. Strict requirements on the development of the digital computer systems in nuclear applications are described.

무선기술의 원전 적용

구인수(In Soo Koo) 표준인증안전학회 2015 표준인증안전학회지 Vol.5 No.2

This standard applies to the I&C of new nuclear power plants and to backfit of I&C in existing plants. Every wireless device or wireless system that is Important to Safety is in the scope of this standard The type of data transferred - voice communications, process data, etc. - is irrelevant, as long it takes part in a safety classified function. Those Important to Safety wireless devices may be fixed or mobile. This standard restricts the use of wireless devices to systems supporting category C functions according to IEC 61226, excluding explicitly their use for categories A and B. The use of wireless technology in nuclear power plants has numerous advantages. Generally, wireless communication technology can be associated with a traditional wiring connection sensor or instnnnent, and has the additional advantage of reducing cabling costs. In spite of these advantages, it is difficult to apply wireless technology in operational NPPs due to problems with cyber security and EMIIRFI. Non-safety devices and systems may use this standard as guidelines, for example to ensure that Important to Safety devices are not disturbed, although its use is not mandatory. Section 4 describes the fundamental requirements of I&C systems for wireless devices. Section 5 specifies the application specific requirements in the plants. Section 6 describes the requirements for the selection and use of wireless devices or wireless communication systems. Section 7 describes the requirements for the qualification of wireless devices and its envirorunent.

원전 극한 환경적용을 위한 필드버스 통신망 요건

조재완(Jai Wan Cho),이준구(Joon-Koo Lee),허섭(Seop Hur),구인수(In Soo Koo),홍석붕(Seok-Boong Hong) 한국IT서비스학회 2009 한국IT서비스학회지 Vol.8 No.2

As the result of the rapid development of IT technology, an on-line diagnostic system using the fieldbus communication network coupled with a smart sensor module will be widely used at the nuclear power plant in the near future. The smart sensor system is very useful for the prompt understanding of abnormal state of the key equipments installed in the nuclear power plant. In this paper, it is assumed that a smart sensor system based on the fieldbus communication network for the surveillance and diagnostics of safety-critical equipments will be installed in the harsh-environment of the nuclear power plant. It means that the key components of fieldbus communication system including microprocessor, FPGA, and ASIC devices, are to be installed in the RPV(reactor pressure vessel) and the RCS(reactor coolant system) area, which is the area of a high dose-rate gamma irradiation fields. Gamma radiation constraints for the DBA(design basis accident) qualification of the RTD sensor installed in the harsh environment of nuclear power plant, are typically on the order of 4kGy/h. In order to use a fieldbus communication network as an ad-hoc diagnostics sensor network in the vicinity of the RCS pump area of the nuclear power plant, the robust survivability of IT-based micro-electronic components in such intense gamma-radiation fields therefore should be verified. An intelligent CCD camera system, which are composed of advanced micro-electronics devices based on IT technology, have been gamma irradiated at the dose rate of about 4.2kGy/h during an hour up to a total dose of 4 kGy. The degradation performance of the gamma irradiated CCD camera system is explained.

DS-CDMA 시스템에서 용량증대를 위한 Sensitivity 연구

구인수(In-Soo Koo),배진(Jin Bae),A. Ahmad,김기선(Kiseon Kim) 한국정보과학회 1997 한국정보과학회 학술발표논문집 Vol.1997 No.4

카오스적인 랜덤신호 발생에 관한 연구

구인수(In-Soo Koo),김환우(Hwan-Woo Kim) 한국산업정보학회 1999 한국산업정보학회논문지 Vol.4 No.3

효과적 채널 검색을 위한 채널 목록 기반 무선 인지 시스템

이영두(Young-du Lee),구인수(In-soo Koo) 대한전기학회 2009 정보 및 제어 심포지엄 논문집 Vol.2009 No.5

In this paper, we consider a cognitive radio system operating as secondary user. It uses an empty channel that is not currently used by primary users having the license to the channel. In the previous works, secondary user looks for an empty channel by choosing any channel in order or randomly and by sensing the channel to distinguish whether primary users are using. But if primary user is fixed type, we will find an empty channel faster than the mentioned channel selecting methods by using a method considering prior information about cases that primary user used the channel, since it is possible to analogize the channel access possibility of primary user according to regular time and position. Therefore, we propose a channel searching method based on the channel list for the purpose of reducing the channel searching time and improving throughput of secondary users. Firstly, we determine a weighting value of each channel based on the history of channel activities of primary users. This value is added to current channel state buffer and we search an empty channel from channel with smallest value to one with the biggest value. Finally, we compare the performances of the proposed method with those of the sequential channel searching and the random channel searching methods in terms of the average channel searching time and the average number of transmissions of secondary user.

적외선 열영상을 이용한 가시광 통신모듈의 고선량 감마선조사에 따른 열화 분석

조재완(Jai-Wan Cho),홍석붕(Seok-Boong Hong),구인수(In-Soo Koo) 제어로봇시스템학회 2011 제어·로봇·시스템학회 논문지 Vol.17 No.12

In this paper, the degradation evaluation method of VLC (Visible Light Communication) wireless module after high dose rate gamma-ray irradiation using the thermal infrared camera is proposed. First, the heating characteristics of the active devices embedded in the VLC wireless module during the condition of normal operation is monitored by thermal infrared camera. By the image processing technique, the trends of the intensity of the heat emitted by the active devices are calculated and stored. The feature of the blob area including the area of the active devices in the thermal infrared image is extracted and stored. The feature used in this paper is the mean value of the gray levels in the blob area. The same VLC module has been gamma irradiated at the dose rate of about 4.0 kGy/h during 72 hours up to a total dose of 288 kGy. And then, the heating characteristics of the active devices embedded in the VLC wireless module after high dose gamma ray irradiation is observed by thermal infrared camera. The high dose gamma-ray induced degradation of the active devices embedded in the VLC module was evaluated by comparing the mean value of the blob area to the one of the same blob area of the VLC module before the gamma ray irradiation.

강인한 카오스 주파수천이 변조회로

구인수(In Soo Koo),박광현(Kwang Hyeon Park),정종은(Chong Eun Chung),이주신(Ju Sin Yi) 대한전자공학회 1995 대한전자공학회 학술대회 Vol.1995 No.12