• Proceedings of the Korean Nuclear Society Conference
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• 2001.05a
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• pp.220.1-220
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• 2001

• Proceedings of the Korean Nuclear Society Conference
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• 2003.05a
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• pp.121.2-121.2
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• 2003

• Proceedings of the Korean Nuclear Society Conference
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• 2005.10a
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• pp.99-100
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• 2005

• Proceedings of the Korean Nuclear Society Conference
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• 2004.10a
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• pp.595-596
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• 2004

Based on the systems and devices which are being developed in the KNICS project, the data communication network (DCN) which is an essential element for the interfaces among the I&C systems. is designed. The traffic load for each network is calculated at the expected maximum traffic condition. The result shows that the utilizations of all networks satisfy the design requirements.

• Proceedings of the Korean Nuclear Society Conference
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• 2001.05a
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• pp.295.1-295
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• 2001

• Nuclear Engineering and Technology
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• v.44 no.5
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• pp.471-482
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• 2012

To assess the risk of nuclear power plant operation and to determine the risk impact of digital systems, there is a need to quantitatively assess the reliability of the digital systems in a justifiable manner. The Probabilistic Risk Analysis (PRA) is a tool which can reveal shortcomings of the NPP design in general and PRA analysts have not had sufficient guiding principles in modelling particular digital components malfunctions. Currently digital I&C systems are mostly analyzed simply and conventionally in PRA, based on failure mode and effects analysis and fault tree modelling. More dynamic approaches are still in the trial stage and can be difficult to apply in full scale PRA-models. As basic events CPU failures, application software failures and common cause failures (CCF) between identical components are modelled.The primary goal is to model dependencies. However, it is not clear which failure modes or system parts CCF:s should be postulated for. A clear distinction can be made between the treatment of protection and control systems. There is a general consensus that protection systems shall be included in PRA, while control systems can be treated in a limited manner. OECD/NEA CSNI Working Group on Risk Assessment (WGRisk) has set up a task group, called DIGREL, to develop taxonomy of failure modes of digital components for the purposes of PRA. The taxonomy is aimed to be the basis of future modelling and quantification efforts. It will also help to define a structure for data collection and to review PRA studies.

• 한국초전도학회:학술대회논문집
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• v.14
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• pp.74-74
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• 2004

• 대한핵의학회:학술대회논문집
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• 1998.11a
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• pp.47.2-47.2
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• 1998

• Nuclear Engineering and Technology
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• v.54 no.12
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• pp.4422-4430
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• 2022

Studying the effects of gamma radiation on the instrumentation and control (I&C) system of a nuclear power plant is critical to the successful and reliable operation of the plant. In the accidental scenario, the adverse environment of ionizing radiation affects the performance of the I&C system and it leads to inaccurate and incomprehensible results. This paper reports the effects of gamma radiation on the AT89C51RD2, a commercial-off-the-shelf 8-bit high-performance flash microcontroller. The microcontroller, selected for the device under test for this study is used in the remote terminal unit for a nuclear power plant. The custom circuits were made to test the microcontroller under different gamma doses using a ⁶⁰Co gamma source in both ex-situ and in-situ modes. The device was exposed to a maximum dose of 1.5 kGy. Under this hostile environment, the performance of the microcontroller was studied in terms of device current and voltage changes. It was observed that the microcontroller device can operate up to a total absorbed dose of approximately 0.6 kGy without any failure or degradation in its performance.

• Proceedings of the KIEE Conference
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• 1998.07b
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• pp.810-812
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• 1998

Analog I&C hardwares in most of nuclear power plants in operation are aging since they were installed 1950's or 1960's. Thus, the replacement of such systems with digital computer-based systems is currently a new trend in nuclear area. This paper will discuss such transition occurring in nuclear I&C area, Comparative study on the digital technique adopted in leading nuclear industries. Its advantage and performance evaluation will be illustrated as well.