Concrete structures of spent nuclear fuel interim storage facility should maintain their ability to shield and structural integrity during normal, off-normal and accident conditions. The concrete structures may deteriorate if the interim storage facility operates for more than several decades. Even if deterioration occurs, the concrete structures must maintain their own functions such as radiation shielding protection and structural integrity. Therefore, it is necessary to establish an analysis methodology that can evaluate whether the deteriorated concrete structure maintains its integrity under not only normal or off-normal condition but also accident condition. In this study, dynamic material testing was conducted on concrete cores extracted from HANARO exterior wall during seismic reinforcement construction. HANARO was constructed at the Korea Atomic Energy Research Institute in 1995, following strict nuclear quality assurance standards. In order to conduct the dynamic material testing of the extracted concrete cores, self-disposal had to be performed because the concrete cores were extracted and stored in a radiation controlled area. A self-disposal application was prepared and submitted based on the radionuclide analysis results, and it was finally approved in April 2023. Then, a test was performed by processing a specimen for dynamic property testing using a self-disposed concrete core. The concrete cores were processed to create specimens for dynamic material testing and the dynamic material testing was performed to obtain stress-strain diagrams according to the strain rate.

HANARO, a multi-purpose research reactor, uses a reflector as heavy water to obtain high neutron flux. Therefore, two ion exchangers were installed to manage the heavy water quality of the reflector system. The operator of HANARO manages it according to the limit value (Conductivity: less than 0.5 mS/m, pH: 5.5~6.5), and if the limit value is not satisfied, the resin must be replaced. The reflector system is in the enclosed structure and it is designed to delay the release of tritium to the outside. Tritium is produced by a nuclear reaction between neutrons and deuterium. Tritium is inhaled into the body in the form of water or vapor, which is likely to cause internal exposure problem. In addition, since tritium spreads to other regions, thorough management is required. Therefore, HANARO measures and manages tritium in Rx and RCI using the bubbler collection method. In this paper, the change in the behavior of tritium due to the replacement of the reflector ion exchanger resin was analyzed. Due to the increase in conductivity of the reflector, the ion exchanger resin was replaced on March 3, 2022. Therefore, the concentration of tritium was measured to be about 5 times higher than usual. It did not exceed the emission limit, and the concentration values of tritium is stably managed by constant monitoring and analysis.

Korea Institute of Nuclear Nonproliferation and Control (KINAC) remains dedicated to providing national and international training to train the workforce in the area of nuclear nonproliferation and security. INSA has also provided a number of nuclear nonproliferation courses for the public such as middle or high school students and teachers, senior government officials, NGOs in the field of nuclear energy, and so on. The recent trend calls for education with high field applicability. Additionally, as interest in nuclear nonproliferation has recently increased, the demand of the public for education is expected to be increased. However, since it is difficult for the public to access nuclear facilities, it is not easy to understand regulatory activities at nuclear facilities. Therefore, KINAC has developed Virtual Reality (VR) content to enhance the public’s understanding of nuclear facilities and on-site inspection activities of KINAC. VR technology is expected to be a new means that can enable the public to access nuclear facilities in spite of some “VR dizziness” usually called “Human Factor”. This paper introduces the composition and function of KINAC’s nuclear nonproliferation VR content for Hanaro Rx in nuclear nonproliferation courses for the public and seeks ways to optimize it based on a one-year operation experience.

HANARO (High-flux Advanced Neutron Application Reactor)는 우라늄의 핵분열 연쇄반응에서 생성된 중성자를 이용하여 다양한 연구개발을 수행하는 열출력 30 MW 규모의 연구용 원자로이다. 탈기탱크는 HANARO의 부속시설에 설치되어 있다. 탈기탱크는 내부환경요인으로 인해 기체오염물질을 발생시킨다. 탈기탱크는 기체오염물질을 허용 가능한 수준 이하로 유지하기위해 필요하며 기체시료채취판넬의 분석기에 의해 모니터링 된다. 응축수가 발생하여 기체시료채취판넬의 분석기 내부로 유입된다면, 분석기의 측정 챔버 내부에 부식이 발생하여 고장을 야기한다. 응축수의 생성 원인은 탈기탱크에 존재 하는 기체가 분석기로 유입되는 과정에서 탈기탱크와 분석기사이 온도 차이다. 응축수 생성을 억제하고 계통 내부에 생성 된 응축수를 효율적으로 제거하기 위해 탈기탱크와 기체시료채취판넬 사이에 히팅시스템이 설치되었다. 이 연구에서 우리는 히팅시스템의 효율성을 알고자 한다. 또한 Wall Condensation Model을 이용하여 유체 입구온도, 외부온도 및 히팅 케이블 설정온도 변화에 따른 파이프 온도와 평균응축량의 변화를 모델링하였다.

경북농업기술원 구미화훼시험장에서 육성한 장미 ‘Hanaro Pink’ 는 분홍색의 ‘Noblesse’를 모본, 황색의 ‘Sahara’를 부본으로 2002년에 인공교배 한 후 2005년부터 2008년까지 4년간 특성검 정을 하여 2008년에 최종 선발되어 ‘Hanaro Pink’로 명명하였다. 분홍색 스탠다드 절화장미 ‘Hanaro Pink’는 화형이 고심형이고 가 시가 거의 없으며 연간 절화수량이 122.7본/m2이며, 절화장 64.0cm, 꽃직경 10.6cm, 줄기직경 6.3mm, 절화수명 13.7일이며 특히, 개화지 중간부의 가시가 아주 적어 취급이 용이하였다.

This study was to apply Hanaro model in the field and explores what changes teachers experience within series of coursework and daily life. Further, the purpose is to provide preliminary data to teachers who desire to gain a changed life and teaching pers

The irradiation tests of materials in HANARO have been performed usually at temperatures below 300℃ at which the RPV(Reactor Pressure Vessel) materials of the commercial reactors such as the light water reactor and CANDU are operated. As VHTR(Very High Temperature Reactor) and SFR (Sodium-cooled Fast Reactor) projects are being carried as a part of the present Gen-IV program in Korea, the requirements for irradiation of materials at temperatures higher than 500℃ are recently being gradually increased. To overcome the restriction in the use at high temperature of the existing Al thermal media, a new capsule with double thermal media composed of two kinds of materials such as Al-Ti and Al- graphite was designed and fabricated more advanced than the single thermal media capsule. At the irradiation test of the capsule, the temperature of the specimens successfully reached 700℃ and the integrity of Al, Ti and graphite material was maintained.

The purpose of this study was to examine the educational impact to students from Hanaro teaching on elementary physical classes by investigating the process of perception changes of students who avo ided the elementary physical classes through Hanaro teac

The fuel test loop consisted an in-pile test section (IPS) and an out-pile system (OPS) is an nuclear fuel irradiation test facility installed in HANARO and its operating temperature and pressure are similar to those of commercial nuclear power plant’s. Penetration pipe connecting the IPS and OPS at the reactor concrete wall is supported by pool-wall pipe support. The existing pool-wall pipe support established in the HANARO have insulations even thought the leak tightness is not ensured. So, the need for an isolation of the insulations from the HANARO cooling water makes the existing pool-wall pipe support newly designed. In this study a structural evaluation for the pool-wall pipe support in accordance with the 2001 ASME B&PV Section III NF is implemented. The most critical primary and secondary stress intensities occur at the modified connection area of the main cooling water pipe and plate ring, but those values are less than the allowable stress. It is concluded that the existing pool-wall pipe support could be modified to a newly designed shape having an isolated insulation from a HANARO cooling water.

The small break loss-of-coolant accidents for the HANARO fuel test loop have been predicted by MARS code. Conservative method was used for the prediction of the loss-of-coolant accidents. The maximum peak cladding temperature was calculated as 1286K, which was lower than the design limit temperature (1477K) of nuclear fuels for the HANARO fuel test loop. The maximum peak cladding temperature occurred for the cold leg break in the HANARO pool. The hydrogen generation and oxidation of the fuel cladding were also negligible. Consequently, it is ensured that the emergency cooling water system for the HANARO fuel test loop is appropriate for the small break loss-of-coolant accidents.

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 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.