• 제목/요약/키워드: research reactor HANARO

검색결과 151건 처리시간 0.031초

Development of fission 99Mo production process using HANARO

  • Lee, Seung-Kon;Lee, Suseung;Kang, Myunggoo;Woo, Kyungseok;Yang, Seong Woo;Lee, Junsig
    • Nuclear Engineering and Technology
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    • 제52권7호
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    • pp.1517-1523
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    • 2020
  • The widely used medical isotope technetium-99 m (99mTc) is a daughter of Molybdenum-99 (99Mo), which is mainly produced using dedicated research reactors from the nuclear fission of uranium-235 (235U). 99mTc has been used for several decades, which covers about 80% of the all the nuclear diagnostics procedures. Recently, the instability of the supply has become an important topic throughout the international radioisotope communities. The aging of major 99Mo production reactors has also caused frequent shutdowns. It has triggered movements to establish new research reactors for 99Mo production, as well as the development of various 99Mo production technologies. In this context, a new research reactor project was launched in 2012 in Korea. At the same time, the development of fission-based 99Mo production process was initiated by Korea Atomic Energy Research Institute (KAERI) in 2012 in order to be implemented by the new research reactor. The KAERI process is based on the caustic dissolution of plate-type LEU (low enriched uranium) dispersion targets, followed by the separation and purification using a series of columns. The development of proper waste treatment technologies for the gaseous, liquid, and solid radioactive wastes also took place. The first stage of this process development was completed in 2018. In this paper, the results of the hot test production of fission 99Mo using HANARO, KAERI's 30 MW research reactor, was described.

Estimation of nuclear heating by delayed gamma rays from radioactive structural materials of HANARO

  • Noh, Tae-yang;Park, Byung-Gun;Kim, Myong-Seop
    • Nuclear Engineering and Technology
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    • 제50권3호
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    • pp.446-452
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    • 2018
  • To improve the accuracy and safety of irradiation tests in High flux Advanced Neutron Application ReactOr (HANARO), the nuclear energy deposition rate, which is called nuclear heating, was estimated for an irradiation capsule with an iridium sample in the irradiation hole in order. The gamma rays emitted from the radioisotopes (RIs) of the structural materials such as flow tubes of fuel assemblies and heavy water reflector tank were considered as radiation source. Using the ORIGEN2.1 code, emission rates of delayed gamma rays were calculated in consideration of the activation procedure for 8 years and 2 months of HANARO operation. Calculated emission rates were used as a source term of delayed gamma rays in the MCNP6 code. By using the MCNP code, the nuclear heating rates of the irradiation capsules in the inner core, outer core, and heavy water reflector tank were estimated. Calculated nuclear heating in the inner core, outer core, and heavy water reflector tank were 200-260 mW, 80-100 mW, and 10 mW, respectively.

OPPORTUNITIES AND CHALLENGES OF NEUTRON SCIENCE AND TECHNOLOGY IN KOREA

  • Lee, Kye-Hong;Park, J.M. Sung-Il;Kim, Hark-Rho;Jun, Byung-Jin;Kim, Young-Jin;Ha, Jae-Joo;Kim, Mahn-Won;Choi, Sung-Min
    • Nuclear Engineering and Technology
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    • 제41권4호
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    • pp.521-530
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    • 2009
  • Neutron science and technology, the utilization of neutron beams for a wide variety of scientific and engineering research ranging from materials and life science to industrial applications, has been one of the key elements of modem science and technology. Currently, the neutron science and technology in Korea is in rapid growth with the operation of the 30 MW High-flux Advanced Neutron Application Reactor (HANARO) at the Korea Atomic Energy Research Institute, which is one of the most powerful nuclear research reactors in the world. Furthermore, a state of the art HANARO cold neutron research facility, which will open a new era for the neutron science and technology in Korea, is expected to become available in 2010. In this paper, the progress of neutron science and technology in Korea is reviewed and its unprecedented new opportunities and challenges in coming years are presented.

한국원자력연구시설을 이용한 방사선학과 대학생 인력양성 (Cultivation of University Students in Radiology Using Research Facilities at KAERI)

  • 신병철
    • 대한방사선기술학회지:방사선기술과학
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    • 제40권3호
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    • pp.501-508
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    • 2017
  • 본 연구는 연구용원자로(하나로)와 국가방사선연구시설을 이용한 전문교육과정을 개발 운영함으로써 방사선학 전공 대학생들에게 전문화된 교육 기회를 제공하고 현장적응 능력을 증진시킬 목적으로 수행되었다. 이를 위해 하나로와 국가방사선연구시설을 이용한 전문 교육과정을 개발하고 운영함으로써 대학생들에게 하나로 활용 기회를 제공하였고, 대학생을 대상으로 하는 방사선학과 실험 실습을 운영함으로써 차세대 전문가를 양성하였다. 방사선학과 대학생들에게 현장실험실습 기회를 제공함으로써 향후 방사선학 연구 분야의 잠재 이용자를 육성하여 방사선학 인력의 저변 확대를 하고자 하였다. 본 실험실습 과정을 위해 서술형 교재와 강의용 교재, 설문지를 개발하고 활용하였다. 2006년부터 2017년까지 방사선학과 대학생을 대상으로 운영된 실험실습교육과정에 714명이 수료하였다. 방사선학과 대학생들을 대상으로 개발 운영되는 교육과정은 하나로와 국가방사선연구시설의 이용을 더욱 활성화하여 궁극적으로 방사선 산업인력의 저변을 확대하고 올바른 정책 결정 및 기술기반을 확립하는 주요 자원이 될 것이며 방사선 분야의 활성화에도 기여하게 될 것이다.

방사성동위원소를 이용한 정유설비 내 촉매유동 특성 및 수직밀도 분포 측정 (Measurement of the Flow Characteristics and Vertical Density Profile of Catalyst in RFCCU by Radioisotope)

  • 문진호;김종범;박장근;정성희
    • 방사선산업학회지
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    • 제5권4호
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    • pp.317-323
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    • 2011
  • Radioisotopes have been widely used throughout industry to optimize processes, solve problems and improve product quality. A gamma scanning technique using radiation via sealed source (Co-60) was carried out in order to investigate vertical density profile of catalyst regenerator of RFCCU. Also through the radiotracer experiments, the flow characteristics of catalyst was measured. The catalyst samples were irradiated with neutron in HANARO reactor to produce lanthanum-140 to be used as radiotracer for tracing the catalyst itself in catalyst regenerator of RFCCU. The radiotracer was monitored around the catalyst regenerator using collimated NaI scintillation detectors. The results of the experiments were used to diagnose the performance of the RFCCU.

수출전략형 연구로의 1차 냉각계통 개념설계 (The Conceptual Design of Primary Cooling System for an Advanced Research Reactor)

  • 박용철;김경련
    • 유체기계공업학회:학술대회논문집
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    • 유체기계공업학회 2005년도 연구개발 발표회 논문집
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    • pp.503-508
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    • 2005
  • An advanced Research Reactor (ARR) consists of an open-tank-type reactor assembly within a light water pool and generates thermal power of 20 MW. The thermal power is including a fission heat in the core, a fuel generated heat temporary stored in the pool, a circulating pumps generated heat and a neutron reflecting heat in the reflector vessel of the reactor. In order to remove the heat load, the primary cooling system will be installed. In this study, the conceptual design of the primary cooling system has been carried out using a design methodology of HANARO within a permissible range of safety. As results, it has been established that the conceptual design of the primary cooling system including design requirements, performance requirements, design restrictions, system descriptions and system operation to maintain the system functions.

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