중생 고품질 내병 다수성 벼 ‘영보(嶺寶)’

박노봉(No-Bong Park),김상열(Sang-Yeol Kim),여운상(Un-Sang Yeo),김정일(Jeong-Il Kim),이지윤(Ji-Yoon Lee),권오덕(Oh-Deog Kwon),박동수(Dong-Soo Park),이종희(Jong-Hee Lee),조준현(Jun-Hyun Cho),송유천(You-Cheon Song),오성환(Seong-Hwan Oh) 한국육종학회 2019 한국육종학회지 Vol.51 No.4

‘Yeongbo’ is a variety of japonica rice (Oryza sativa L.) with good eating quality, resistance to rice stripe virus, rice dwarf virus, and bacterial blight disease. It was developed by the rice breeding team of the Yeongdeok Branch, National Institute Crop Science, Rural Development Administration in 2014. This variety was derived from a cross between ‘Yeongdeog35’ with good eating quality and ‘Saekyehwa’ with good plant type in the 2002 summer season. A promising line selected through the pedigree breeding method, YR24269-1-2-1-2-3-3, was designated as ‘Yeongdeog57’ in 2011. After a local adaptability test at nine locations from 2012 to 2014, ‘Yeongdeog57’ was released under the name of ‘Yeongbo’ in 2014. ‘Yeongbo’ had a short culm length of 66 cm and medium growth duration. This variety was resistant to K1, K2, and K3 races of bacterial blight, rice stripe virus, and dwarf virus, and moderately resistant to leaf blast disease. ‘Yeongbo’ had translucent and clear milled rice kernel without white core and belly, and good eating quality according to a panel test. The yield potential of ‘Yeongbo’ in milled rice was approximately 5.75 MT/ha at an ordinary fertilizer level in the local adaptability test. This cultivar would be adaptable to middle plain area, south plain area, Yeongnam plain area, east costal area, and south mid-mountainous area. (Registration No.6804)

수축저감제 혼입률 변화에 따른 콘크리트의 공학적 특성에 관한 연구

한민철,金光華,정규문,정평유,윤성노,한천구 대한건축학회 2003 대한건축학회 학술발표대회 논문집 - 계획계/구조계 Vol.23 No.2

In this paper, tests are carried out using concrete incorporating shrinkage reducing agent(SR) in order to investigate the engineering properties of concrete. The contents of SR and W/C are varied. According to test results, as for fresh concrete, as SR content increases, slump and air content shows decline tendency, and setting time is accelerated with increase of SR content and decrease of W/C. As for compressive strength, as SR contents increases compressive strength shows to be decreased. As for the effect of SR on drying shrinkage, it shows to be reduced with increase of SR content. This is due to the reduced surface tensile strength of water and tensile strength of capillary pore in concrete.

Interrelationship Between the Drift-flux Model and the Two-fluid Model

No, Hee-Cheon Korean Nuclear Society 1993 Nuclear Engineering and Technology Vol.25 No.2

상 변화가 없고 압력 변화가 없는 일차원 이상 유동에 있어서 드리프트 플럭스 모델자 2-유체 모델 사이의 상관 관계가 연구되었다. 증기 보존식은 드리프트 플럭스를 통하여 운동량 보존식에 의존한다는 사실에 기초하여 관계가 얻어졌다. 2-유체 모델로부터 출발하여 트리프트 플럭스의 파라미터의 함수로 표현된 계면 마찰식을 얻었다. 또한 기공 전달식을 유도함으로써 드리프트 플럭스는 2-유체 모델의 마찰력과 상호 관계가 있음을 보였다.

Observation-based CHF model development: Dry spot – Dry patch models

No, Hee Cheon,Song, Moon Won,Ha, Sang-Jun,Ju, In-Chul,Choi, Jin Young Elsevier 2019 Nuclear engineering and design Vol.342 No.-

<P><B>Abstract</B></P> <P>Recently advanced visualization techniques such as total reflection and IR methods have been applied to observe thermally and hydraulically the CHF mechanism at the surface as well as macroscopic bubble dynamics simultaneously. Based on observation Ha and No (1998a,b, 2000), and Choi et al. (2016) developed a Dry spot model and a Dry patch model, which is an extension version of the dry spot model. Experimental observations clearly showed that the production of unquenchable dry patches mainly contributes to the initiation of CHF.</P> <P>Based on the above observatory conclusions and extensive literature survey, we discussed the physical basis of the Dry Spot/Dry Patch model. In the dry spot model, we assume that the dry spot can become unquenchable one when it is surrounded by 5 neighboring dry spots based on the geometrical consideration, which was confirmed by validation process. In the dry patch model, both criteria from the hydraulic and thermal considerations were proposed to estimate the critical size of unquenchable dry patch at CHF. The wall dry area fraction can be calculated by applying a probabilistic concept for the creation of the unquenchable dry patch. We showed that the Dry Spot/Dry Patch model can be extended into CHF predictions in both pool boiling and forced convective boiling. For transition boiling, we proposed models to represent two suppression mechanisms deactivating potential nucleation sites: nucleation site deactivation and non-availability mechanism. For the physical model of the nucleation site deactivation mechanism we introduced the spatial randomness concept. For the non-availability mechanism we proposed the multi-stage calculation method which considers the sequential bubble activation and their interaction. Then, we showed that the dry spot model modified with the current transition model well predicted the whole boiling curve including CHF, nucleate boiling, transition boiling, and film boiling.</P> <P><B>Highlights</B></P> <P> <UL> <LI> Several observations supporting the Dry Spot/Dry Patch models were introduced. </LI> <LI> Based on the observation the physical basis for the Dry Spot model was described. </LI> <LI> The Dry Spot and Dry Patch models well predict CHF for pool and convective boiling. </LI> <LI> Using the concept of the suppression of NSD, the whole boiling curve was predicted. </LI> </UL> </P>

A REVIEW OF HELIUM GAS TURBINE TECHNOLOGY FOR HIGH-TEMPERATURE GAS-COOLED REACTORS

No, Hee-Cheon,Kim, Ji-Hwan,Kim, Hyeun-Min Korean Nuclear Society 2007 Nuclear Engineering and Technology Vol.39 No.1

Current high-temperature gas-cooled reactors (HTGRs) are based on a closed Brayton cycle with helium gas as the working fluid. Thermodynamic performance of the axial-flow helium gas turbines is of critical concern as it considerably affects the overall cycle efficiency. Helium gas turbines pose some design challenges compared to steam or air turbomachinery because of the physical properties of helium and the uniqueness of the operating conditions at high pressure with low pressure ratio. This report present a review of the helium Brayton cycle experiences in Germany and in Japan. The design and availability of helium gas turbines for HTGR are also presented in this study. We have developed a new throughflow calculation code to calculate the design-point performance of helium gas turbines. Use of the method has been illustrated by applying it to the GTHTR300 reference.

HORIZON EXPANSION OF THERMAL-HYDRAULIC ACTIVITIES INTO HTGR SAFETY ANALYSIS INCLUDING GAS-TURBINE CYCLE AND HYDROGEN PLANT

No, Hee-Cheon,Yoon, Ho-Joon,Kim, Seung-Jun,Lee, Byeng-Jin,Kim, Ji-Hwang,Kim, Hyeun-Min,Lim, Hong-Sik Korean Nuclear Society 2009 Nuclear Engineering and Technology Vol.41 No.7

We present three nuclear/hydrogen-related R&D activities being performed at KAIST: air-ingressed LOCA analysis code development, gas turbine analysis tool development, and hydrogen-production system analysis model development. The ICE numerical technique widely used for the safety analysis of water-reactors is successfully implemented into GAMMA, with which we solve the basic equations for continuity, momentum conservation, energy conservation of the gas mixture, and mass conservation of 6 species (He, N2, O2, CO, CO2, and H2O). GAMMA has been extensively validated using data from 14 test facilities. We developed a tool to predict the characteristics of HTGR helium turbines based on the throughflow calculation with a Newton-Raphson method that overcomes the weakness of the conventional method based on the successive iteration scheme. It is found that the current method reaches stable and quick convergence even under the off-normal condition with the same degree of accuracy. The dynamic equations for the distillation column of HI process are described with 4 material components involved in the HI process: H2O, HI, I2, H2. For the HI process we improved the Neumann model based on the NRTL (Non-Random Two-Liquid) model. The improved Neumann model predicted a total pressure with 8.6% maximum relative deviation from the data and 2.5% mean relative deviation, and liquid-liquid-separation with 9.52% maximum relative deviation from the data.

AN EXPERIMENTAL STUDY ON AIR-WATER COUNTERCURRENT FLOW LIMITATION IN THE UPPER PLENUM WITH A MULTI-HOLE PLATE

NO HEE CHEON,LEE KYUNG-WON,SONG CHUL-HWA Korean Nuclear Society 2005 Nuclear Engineering and Technology Vol.37 No.6

Air-water countercurrent flow limitation at perforated plates with four holes was investigated in a vertical tank to see the effects of the plate thickness, the number of hole, and the diameter of the hole on the onset of CCFL. The thickness of plates was 1 cm and 4 cm, with a relatively large hole diameter of 5 cm. The collapsed water level formed on the perforated plate and its distribution in the upper plenum were measured. The gas flow rate in the multi-hole plate is relatively higher than one in the single tube because some of holes in the multi-hole plate provide a flow path fur liquid with less air-liquid resistance than in the single tube. The onset of CCFL occurred at nearly the same air flow rate regardless of the plate thickness. The negligible effect of the plate thickness on CCFL means that the flooding is initiated at the top of the plate rather than at its bottom. It turns out that $j_k$ and $K_k$ better fit the data than $H_k$ when hole diameter is greater than 2.86 cm. In our experimental ranges, the collapsed water levels at the onset of CCFL ranged from 7.5 cm to 10.5 cm. There was no three dimensional distribution of water level before and after the onset of CCFL.

그리드 요소 크기에 따른 1방향 탄소그리드 보강 콘크리트 슬래브의 휨거동

노시천(No, Si-Cheon),이수민(Lee, Su-Min),장소영(Jang, So-Yeong),김선우(Kim, Sun-Woo),박완신(Park, Wan-Shin),윤현도(Yun, Hyun-Do) 한국콘크리트학회 2023 한국콘크리트학회 학술대회 논문집 Vol.35 No.2

Decay Beat Removal and Operator's Intervention During A Very Small L()CA

Hee Cheon No Korean Nuclear Society 1984 Nuclear Engineering and Technology Vol.16 No.1

매우 작은 규모의 냉각재 상실 사고후($\leq$0.05ft$^2$) 어떤 일이 일어나는 가를 더 잘 이해하기 위해 고리 1호기에 대한 샘플 계산을 수행하였다 깨진 크기가 0.006 ft$^2$ 보다 큰 사고에 대해서는 냉각재 상실이 보충되는 양을 초과한다. 0.008 ft$^2$ 보다 큰 깨진 크기에 대해서는 잔열은 깨진 곳을 통해 완전히 제거된다. 이와 같은 결과에 비추어 고리 1호기는 매우 작은 규모의 냉각재 상실 사고의 전 영역에 걸쳐 비교적 안전하다고 결론지었다. 하지만, 900MWe 나 1200MWe 를 가진 원자로에 있어서, 어떤 깨진 크기에 대해서는 이 사고가 주의깊게 고려되어야 한다. 자연 순환에서 pool boiling 으로 또는 pool boiling에서 자연 순환으로 천이할때, 특별히 운전자와 안전 분석에 문제점을 남긴다. Primary pump shutoff, HPI pump shutoff, break isolation, opening relief valve의 운전자 간섭에 대해서도 논의 되었다. Shutoff 후 HPI pump의 연속적인 운전은 primary system의 건전성을 위협하지 않는다는 것이 증명되었다. Sample calculations were done for KORI-1 to develop a better understanding of what happens after very small LOCA ($\leq$0.05 ft$^2$). For a water-side break with the break size larger than 0.006 ft$^2$, fluid-loss through break exceeds the makeup. If the break size is larger than 0.008ft$^2$, decay heat can be completely removed through break. Based on these results, it was concluded that KORI-1 is fairly safe for the whole spectrum of sizes in very small LOCA. However, for the reactor with 900 MWe or 1200 MWe, a certain spectrum of sizes in very small LOCA should be carefully considered. In the accident sequence the transition from natural circulation to pool boiling or from pool boiling to natural circulation may be troublesome to the operator or in the safety analysis. Operator's intervention was discussed; primary pump shutoff, HPI pump shutoff, break isolation, and opening relief valve. It was proved that continuous operation of HPI pumps after shutdown will not threaten the integrity of the primary system.

Study of the RBTRAN Code for Upper Plenum Analysis in Very Small LOCA

Hee Cheon No Korean Nuclear Society 1984 Nuclear Engineering and Technology Vol.16 No.3

매우 작은 규모 LOCA 분석에 RETRAN코드 적용에 있어서 중요 문제점의 하나는 upper plenum에 Bubble rise model의 사용에 있다. 왜냐하면, Bubble rise model은 수리적 발산을 야기할지 모르며, 그 모텔에 사용되는 계수는 큰 규모 냉각재 상실 사고의 실험적 결과에 바탕을 두기 때문이다. 여기서, Bubble rise model을 사용하지 않고 upper plenum의 mixture level을 예측하게 해주는 방법이 제시되었다. 이 방법을 위해 노심과 upper plenum내의 지역 void 분포가 간단한 slip 모델을 이용 괘 유도되었다. 유도된 식으로부터의 결과는 실험 데이타와 매우 잘 일치한다는 것이 발견되었다. 또한, Upper Plenum에 있어서 지역 void는 대규모 LOCA에 있어서 선형 분포와는 달리 균일한 분포를 하고 있다는 것이 발견되었다. upper plenum과 upper head사이의 냉각재 교환이 연구되었다. Taylor instability 개념 도입에 의해 그들 사이에 counter-current flow가 가능하다는 것이 증명되었다. In the application of the RETRAN code to the analysis of very small LOCA one of main concerns is placed on use of the bubble rise model in the upper plenum, because the bubble rise model nay cause a numerical divergence problem and coefficients used to describe it are based on experimental results of large LOCA. In order to solve this problem, a method, which enables us to predict the mixture level in the upper plenum without use of the bubble rise model, was proposed. For this method the local void distribution in the core and upper plenum was derived by using a simplified slip model. It was shown that results predicted from the derived equation are in excellent agreement with experimental data. Additionally it was found that local void in the upper plenum has a uniform distribution unlike a linear distribution in large LOCA. Communication between the upper plenum and upper head was investigated. By introducing the concept of Taylor instability, it was proved that counter-current Hon between them is possible.