• 대한방사선방어학회:학술대회논문집
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• 2009.11a
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• pp.226-227
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• 2009

• Proceedings of the Korean Information Science Society Conference
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• 2006.06c
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• pp.229-231
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• 2006

본 논문은 한국원자력연구소 내에서 가동 중인 하나로 원자로의 방사선감시시스템 소프트웨어 개발에 있어서 속성기반설계를 적용한 사례를 소개한다. 본 논문에서 채택한 속성기반설계는 시스템의 기능요건 및 품질요건 도출, 이를 만족하기 위한 전술 설정, 설정된 전술에 근거하여 시스템 아키텍처 결정, 확정된 아키텍처를 구현 및 검증하는 과정으로 이루어진다. 하나로 방사선감시시스템의 개발요건으로부터 사용성, 가용성, 유지보수성. 호환성, 확장성 과 같은 품질속성을 추출하였으며, 개발 전술로는 이중화된 서버에 다수의 클라이언트가 연결되는 클라이언트-서버클러스터링 전술과 객체지향적 데이터 처리 및 디스플레이 설계 전술을 채택하였다. 단기간 내에 개발을 완수해야하는 방사선감시시스템 개발에 속성기반설계를 적용함으로써 보다 효율적으로 과제를 성공시킬 수 있었다.

• 대한방사선방어학회:학술대회논문집
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• 2010.04a
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• pp.184-185
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• 2010

• Journal of the Korean Society of Radiology
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• v.14 no.3
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• pp.279-287
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• 2020

Recently, interest in radiation protection is increasing because of the occurrence of accidents related to exposure dose. So, the nuclear safety act provides to install the shields to avoid exceeding the dose limit. In particular, when the worker conducts the non-destructive testing (NDT) without the fixed shielding structure, we should monitor the access to the workplace based on a constant dose rate. However, when we apply for permits for NDT work in these work environments, the consideration factors to the estimation of the distance and exposure dose are not legally specified. Therefore, we developed the excel model that automatically calculates the distance, exposure dose, and cost if we input the factors. We applied the assumption data to this model. As a result of the application, the distance change rate was low when the thickness of the lead blanket and collimator is above 25 mm, 21.5 mm, respectively. However, we didn't consider the scattering and build-up factor. And, we assumed the shape of the lead blanket and collimator. Therefore, if we make up for these limitations and use the actual data, we expect that we can build a database on the distance and exposure dose.

• Proceedings of the Korean Radioactive Waste Society Conference
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• 2003.11a
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• pp.406-410
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• 2003

DUPIC Fuel Development Facility(DFDF) is the facility to fabricate CANDU-type fuel from spent PWR fuel material without any separation of fissile elements and fission products. Unattended continuous surveillance systems for safeguards of nuclear facility result in large amounts of image and radiation data, which require much time and effort to inspect. Therefore, it is necessary to develop system that automatically pinpoints and diagnoses the anomalies from data. In this regards, this paper presents a novel concept of the continuous surveillance system that integrates visual image and radiation data by the use of neural networks. This surveillance system is operating for safeguards of the DFDF in KAERI.

• 대한방사선방어학회:학술대회논문집
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• 2009.11a
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• pp.72-73
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• 2009

• 대한방사선방어학회:학술대회논문집
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• 2011.11a
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• pp.146-147
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• 2011

• Journal of Radiation Protection and Research
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• v.14 no.1
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• pp.75-83
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• 1989

• The KIPS Transactions:PartD
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• v.14D no.1 s.111
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• pp.121-130
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• 2007

in a software development, the design or architecture prior to implementing the software is essential for the success. This paper presents a case that we successfully designed a software architecture of radiation monitoring system (RMS) for HANARO research reactor currently operating in KAERI by applying the quality attribute-driven design method which is modified from the attribute-driven design (ADD) introduced by Bass[1]. The quality attribute-driven design method consists of following procedures: eliciting functionality and quality requirements of system as architecture drivers, selecting tactics to satisfy the drivers, determining architectures based on the tactics, and implementing and validating the architectures. The availability, maintainability, and interchangeability were elicited as duality requirements, hot-standby dual servers and weak-coupled modulization were selected as tactics, and client-server structure and object-oriented data processing structure were determined at architectures for the RMS. The architecture was implemented using Adroit which is a commercial off-the-shelf software tool and was validated based on performing the function-oriented testing. We found that the design method in this paper is an efficient method for a project which has constraints such as low budget and short period of development time. The architecture will be reused for the development of other RMS in KAERI. Further works are necessary to quantitatively evaluate the architecture.

• Proceedings of the KIEE Conference
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• 2000.07a
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• pp.555-557
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• 2000

원자력 발전소에서 사용되어지는 케이블은 전원 및 제어신호를 안정하게 전달하는 역할을 하며, 비상상태 발생시에는 원자로를 안전하게 shut-down시키는 통로 역할을 하므로 매우 중요하다. 케이블 상태 감시시 절연 및 피복재료는 종류 및 배합내용이 다양하기 때문에 종래의 자료로부터 전선과 케이블의 열화 또는 수명을 추정하기가 극히 어려우며 방사선에 노출이 되는 케이블의 경우 노화현상의 진행이 빠르고 방사선 열화로 수명이 단축되므로 국내 실정을 감안한 독자적인 검증방법 도출, 규제기술 기반 구축 필요 및 규제의 합리화와 효율화 필요성이 대두되고 있다. 기존에 사용해온 케이블 진단 방법에는 절연 파괴 강도 측정을 통한 노화진단, 산화 방지능력 측정을 통한 노화진단, 자켓 및 절연체의 판단, 연신율에 의한 노화진단, 케이블 Indenter에 의한 노화진단, 온도 및 방사선 등의 특정상태에 대한 평가, 유사한 환경조건에 대한 주기적 검토 등이 있다. 기존의 국내외 케이블 상태 감시방법을 조사 연구하므로서 케이블 열화에 대비한 수명관리 규제 기술 및 상태감시 (Condition Monitoring : CM) 기술의 평가 기준을 결정 하고자 한다.