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.

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 is consisted of In-Pile Section(IPS) and Out-of Pile System(OPS). The IPS which is localed inside the pool is divided into 3-parts; they are in-pool pipes, 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 collant pressure boundary. The localization of the IVA is achieved by manufacturing through local company and the functional test and verification were done through pressure drop, vibration, hydraulic and leakage tests. The brazing technique of the instrument lines has been checked for its functionality and yield. A IVA has been manufactured by local technique and will be finally tested under out of the high temperature and high pressure test.

The nuclear fuel cladding temperatures of the HANARO fuel test loop have been calculated by MARS code for the large break loss-of-coolant accidents. Conservative method was used for the analysis of the loss-of-coolant accidents. Consequently, the maximum peak cladding temperature was predicted as 1235K, which was lower than the design limit temperature (1477K) of nuclear fuels for the HANARO fuel test loop. This means that the cooling capability of the emergency cooling water system for the HANARO fuel test loop is sufficient for the large break loss-of-coolant accidents.

The conservative method on the analysis of loss-of-coolant accidents for the HANARO fuel test loop was established based on the guide of evaluation method for the emergency core cooling systems of pressurized light water reactors. The evaluation models, the Moody model for discharge rate calculation and the Baker-Just model for water-metal reaction calculation, were used. In order to calculate conservative peak cladding temperatures for accidents the multipliers to the correlations of heat transfer coefficients in the MARS were also introduced. Consequently it is found that the maximum peak cladding temperature predicted by using the conservative method is sufficiently greater than that calculated by using the best-estimated models.

It is essential to develop the shield for the extraction of high quality neutron beam and safe work at the sample position. The aim of this study is design, fabrication and filling of the shield in domestic. In consideration of ST-3 beam port of HANARO, we designed the reflectometer shield composed of 14 blocks and fabricated it shield casemate. Through the assembly and quality test of the shield casemate, we established the method of fabrication for neutron beam path and channel. In order to increase shield capacity, we filled shield casemate with heavy concrete, lead ingot and polyethylene that mixed B4C powder and epoxy. The average density of the filled heavy concrete was 4.7g/cm3, which can protect neutron and gamma ray effectively. Also, we developed ancillary equipment such as beam gate unit(BGU, vertical type) for the effective opening and closing of neutron beam. Shielding block was proved by suitable thickness as result that measure surface dosage using of detector and TLD. The acquired technique of design, fabrication and filling of ancillary equipment development can be applicable to the development of shield for the other neutron spectrometer in future.

재료나 핵연료조사시험에서 다공원통형구조물의 모든 구성품에서 감마열 및 fission과 같은 열원이 발생한다. 본 연구는 조사시험중 다공원통형구조물의 열적건전성을 평가하기 위해 온도분포에 대한 일반해를 구하는데 그 목적이 있다. 다공원통형 구조물의 온도해석을 위해 2차원 열전토 방정식을 이용하였다. 유한요소해석은 ANSYS 6.1을 이용하여 수행하였다. 다공원통형 구조물의 온도해석에서 이론해석결과와 유한요소해석결과는 홀의 개수가 3개 이하에서는 온도가 서로 잘 일치하는 것으로 나타났다. 구조물의 홀 개수가 4개일때, 온도분포해석에 대한 두 결과의 차이가 증가하였다.