• Journal of the KSME
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• v.33 no.5
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• pp.393-404
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• 1993

원자로 압력용기의 수명 및 건전성을 결정짓는 중성자 조사취화현상에 대해 손상과정, 기구, 영 향인자, 예측 및 평가방법을 소개하였다. 용기재료의 현상, 특성과 설계, 제조, 운전시의 건전성 확보를 위한 활동 및 방법도 함께 살펴보았다. 설계시는 물론 수명기간 동안 건전성을 유지하 면서 운전하고 나아가 수명연장 운전을 위해서는 용기의 상태(파괴인성치, 결함, 작용응력)를 정확히 진단, 예측, 평가해야 하고, 이들이 건전성에 미치는 영향평가와 건전성 평가방법을 통한 수명예측 기술의 확보가 매우 중요하다. 특히, 고리 1호기가 가동된지 15년이 되어 계속적인 감 시가 요구되고 수명연장 타당성 연구를 추진중에 있으며, 영광 3, 4호기를 시작으로 앞으로 건 설되는 원자로가 국내에서 제작 . 설치되고, 설계 및 소재의 국산화율을 높이고자 하는 우리나 라에서는 더욱 그러하다. 미소시험법 및 시편재활용 기술개발을 통한 시험자료의 확충과 국내 원자로에 대한 데이터베이스 구축 및 각 발전소 특유의 경향곡선 확립 . 적용이 필요하며, 조사 손상 기구 및 모델링 관련연구가 계속되어야 한다. 조사효과에 대한 기초 및 응용연구는 1994년 한국원자력연구소의 다목적연구용원자로(MRR ; multipurpose research reactor) 가동과 더불어 더욱 활발해질 것이다.

• Journal of the KSME
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• v.49 no.11
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• pp.45-51
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• 2009

한국원자력연구원의 다목적 연구용 원자로, 하나로는 중성자 이용 물성 연구 등 다양한 분야에 사용되며, 중성자는 녹색기술 관련 소재의 생산과 특성 분석에 매우 유용한 도구이다. 중성자 도핑을 이용하여 생산되는 반도체는 그린 카에 사용되는 전력 소자에 활용되고 있다. 중성자 산란 실험 장치들은 이차전지 재료와 수소저장 물질의 물성 연구에 활용되고 있다. 중성자 비파괴 검사 장치는 연료전지의 성능 연구에 활용되고 있다. 고속중성자를 이용하여 스위칭 소자의 특성을 개선하는 기술과 장치가 구축되면 전력 소자의 효율 증대에 기여할 것이다.

• Proceedings of the Korean Society for Noise and Vibration Engineering Conference
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• 1990.10a
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• pp.125-128
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• 1990

조사후 시험시설(Post Irradiated Examination Facility, PIEF)은 내진범주 1 급 구조물로서 현재 각종 실험 및 연구가 진행중인 원자력 안전관련시설물 이다. 한편 이 건물로부터 30m - 120m 정도 떨어져 있는 다목적연구로 (Korea Multipurpose Research Reactor, KMRR) 및 조사재시험시설 (Irradiation Material Examination Facility, IMEF)의 건조사업을 위하여 기 초암반의 굴착작업을 수행할 경우 발파작업에 따른 그 진동 및 폭풍압영향 이 염려되어, 그 안전성 평가를 위하여 시험발파를 수행해야 할 필요가 제기 되었다. 우선 운전중인 원자력안전 시설물에서의 발파에 따른 진동허용 기준 을 설정하고, 둘째로 거리에 따른 폭발량을 경험식에 따라 잠정 결정한 후, 세째로 시험발파에 의한 진동 측정을 수행하여 그 영향을 평가하고, 끝으로 이에 따라 거리별 제한 폭발량을 결정한후 실제 본발파에 적용하고자 한다. 이로써 운전중인 원자력 안전관련시설물인 PIEF의 안전 운전을 도모하고 KMRR및 IMEF 시설의 건조를 원만하게 이룰 수 있을 것이다.

• Transactions of the Korean Society of Mechanical Engineers A
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• v.33 no.2
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• pp.179-184
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• 2009

The Fuel Test Loop(FTL) which is capable of an irradiation testing under a similar operating condition to those of PWR(Pressurized Water Reactor) and CANDU(CANadian Deuterium Uranium reactor) nuclear power plants has been developed and installed in HANARO, KAERI(Korea Atomic Energy Research Institute). It consists of In-Pile Section(IPS) and Out-of Pile System(OPS). The IPS, which is located inside the pool is divided into 3-parts; the in-pool pipes, the IVA(IPS Vessel Assembly) and the support structures. The test fuel is loaded inside a double wall, inner pressure vessel and outer pressure vessel, to keep the functionality of the reactor coolant pressure boundary. The IVA is manufactured by local company and the functional test and verification were done through pressure drop, vibration, hydraulic and leakage tests. The brazing technique for the instrument lines has been checked for its functionality and performance. An IVA has been manufactured by local technique and have finally tested under high temperature and high pressure. The IVA and piping did not experience leakage, as we have checked the piping, flanges, assembly parts. We have obtained good data during the three cycle test which includes a pressure test, pressure and temperature cycling, and constant temperature.

• Proceedings of the SAREK Conference
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• 2007.11a
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• pp.310-315
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• 2007

The FTL has been developed to be able to irradiate test fuels at the irradiation hole(IR1 hole) by considering its utility and user's irradiation requirements. FTL consists of In-Pile Test Section (IPS) and Out-of-Pile System (OPS). Test condition in IPS such as pressure, temperature and the water quality, can be controlled by OPS. For safety assurance IPS is designed to have dual stainless steel pressure vessel and OPS is composed of main cooling water system, emergency cooling water system, LMP(letdown, make-up, purification) system, etc. FTL Conceptual design was set up in 2001, basic design had completed including a design requirement, basic piping & instrument diagram (P&ID), and the detail design in 2004. In 2005, the development team carried out purchase and manufacture hardware and make a contract for construction work. FTL construction work began on August, 2006 and ended on March, 2007. After FTL development which is expected to be finished by 2008, FTL will be used for the irradiation test of the new PWR-type fuel and can maximize the usage of HANARO.

• Proceedings of the KSME Conference
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• 2007.05a
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• pp.291-295
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• 2007

FTL(Fuel Test Loop) is a facility that confirms performance of nuclear fuel at a similar irradiation condition with that of nuclear power plant. FTL consists of In-Pile Test Section (IPS) and Out-Pile System (OPS). FTL construction work began on August, 2006 and ended on March, 2007. During Construction, ensuring the worker's safety was the top priority and installation of the FTL without hampering the integrity of the HANARO was the next one. Task Force Team was organized to do a construction systematically and the communication between members of the task force team was done through the CoP(community of Practice) notice board provided by the Institute. The installation works were done successfully overcoming the difficulties such as on the limited space, on the radiation hazard inside the reactor pool, and finally on the shortening of the shut down period of the HANARO. Without a sweet of the workers of the participating company of HEC(Hyundae Engineering Co, Ltd), HDEC(HyunDai Engineering & Construction Co. Ltd), equipment manufacturer, and the task force team, it is not possible to install the FTL facility within the planned shutdown period. The Commissioning of the FTL is on due to check the function and the performance of the equipment and the overall system as well. The FTL shall start operation with high burn up test fuels in early 2008 if the commissioning and licensing progress on schedule.

• Proceedings of the SAREK Conference
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• 2007.11a
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• pp.305-309
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• 2007

FTL(Fuel Test Loop) is a facility that confirms performance of nuclear fuel at a similar irradiation condition with that of nuclear power plant. FTL construction work began on August, 2006 and ended on March, 2007. During Construction, ensuring the worker's safety was the top priority and installation of the FTL without hampering the integrity of the HANARO was the next one. The installation works were done successfully overcoming the difficulties such as on the limited space, on the radiation hazard inside the reactor pool, and finally on the shortening of the shut down period of the HANARO. The Commissioning of the FTL is to check the function and the performance of the equipment and the overall system as well. The FTL shall start operation with high burn up test fuels in early 2008 if the commissioning and licensing progress on schedule.

• Nuclear Engineering and Technology
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• v.23 no.3
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• pp.328-339
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• 1991

A multi-purpose research reactor called KMRR has been developed by Korea Atomic Energy Research Institute(KAERI) to generate a maximum thermal output of 30 MW. As a part of thermal hydraulics study, pressure drop characteristics of the longitudinally finned fuel rod bundles were experimentally investigated in a recirculating water test loop. The present study is focused on the investigation of fin effects on pressure drop and the development of pressure drop correlation for the finned rod bundles in a wide range of flow conditions. Friction factor correlations for each design of the finned rod bundles are developed. The value of friction factor for the finned rod bundles was higher than the analytical solution (64/Re) of laminar circular channel new but became lower than the Blasius equation as Reynolds number was increased.

• Nuclear Engineering and Technology
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• v.26 no.4
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• pp.526-535
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• 1994

For the evaluation of the corrosion behavior of the aluminum cladding in the KMRR(Korea Multipurpose Research Reactor) fuel, a modified Griess correlation was derived by introducing a heat flux factor derived from the comparison of the measured in-reactor corrosion data with the prediction of the Griess correlation. As a design criterion on the corrosion to maintain the KMRR fuel integrity, prevention of the oxide spallation was conservatively selected, which is conservatively assumed to occur when the temperature difference across the oxide layer exceeds 114$^{\circ}C$. A bounding power history of the KMRR fuel was determined by examining all the power histories of the KMRR fuel from cycle 1 to equilibrium cycle, and used to predict the maximum possible corrosion. Results of the corrosion prediction of the KMRR fuel with the bounding power history showed that the maximum local thickness of the oxide layer would be below 50$\mu$m and the design criterion on the oxide spallation would be satisfied with a factor of two margin. Therefore, it can be said that corrosion of the cladding will not impair the integrity of the KMRR fuel. Nevertheless, the applicability of the modified Griess correlation to the KMRR needs to be further verified through the KMRR fuel corrosion surveillance.

• Progress in Medical Physics
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• v.18 no.2
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• pp.87-92
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• 2007

A thermal neutron beam facility utilizing a typical tangential beam port for Neutron Capture Therapy was installed at the HANARO, 30 MW multi-purpose research reactor. Mixed beams with different physical characteristics and relative biological effectiveness would be emitted from the BNCT irradiation facility, so a quantitative analysis of each component of the mixed beams should be performed to determine the accurate delivered dose. Thus, various techniques were applied including the use of activation foils, TLDs and ionization chambers. All the dose measurements were perform ed with the water phantom filled with distilled water. The results of the measurement were compared with MCNP4B calculation. The thermal neutron fluxes were $1.02E9n/cm^2{\cdot}s\;and\;6.07E8n/cm^2{\cdot}s$ at 10 and 20 mm depth respectively, and the fast neutron dose rate was insignificant as 0.11 Gy/hr at 10 mm depth in water The gamma-ray dose rate was 5.10 Gy/hr at 20 mm depth in water Good agreement within 5%, has been obtained between the measured dose and the calculated dose using MCNP for neutron and gamma component and discrepancy with 14% for fast neutron flux Considering the difficulty of neutron detection, the current study support the reliability of these results and confirmed the suitability of the thermal neutron beam as a dosimetric data for BNCT clinical trials.