• Proceedings of the Korea Institute of Fire Science and Engineering Conference
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• 2011.04a
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• pp.267-271
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• 2011

국내에서는 고층 건축물의 화재시 피난계단으로의 연기침투를 방지하여 안전한 피난경로를 확보하기 위하여 피난계단의 부속실에 외기를 급기함으로써 부속실을 단독으로 제연하는 급기가압 제연시스템을 주로 사용하고 있다. 그러나 실제 건축물에 설치되어 운영되고 있는 급기가압 제연시스템에 대한 현장 성능평가의 결과를 검토해보면 상당수의 건축물에서 급기가압 제연시스템이 소기의 운전성능을 발휘하지 못하고 있음을 알 수 있다. 즉, 제연구역인 부속실과 옥내간의 차압이 기준치 이상의 과압으로 형성되거나 또는 반대로 기준치 이하의 저압으로 유지되는 경우가 있다. 특히 피난에 따라 부속실의 출입문이 개방되면, 출입문이 열린 층 이외의 층에서 개방 전에 적정한 수준으로 유지되고 있던 차압이 크게 하강하는 것을 알 수 있다. 본 논문에서는 이러한 급기가압 제연시스템의 문제점과 이에 대한 개선방향을 검토하였다.

• Journal of Radiation Protection and Research
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• v.40 no.4
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• pp.267-276
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• 2015

Several analyses on tritium that is the largest release of gas or liquid radioactive waste from domestic PWR and PHWR NPPs were carried out, such as release comparison, directional frequency of wind and tritium behavior changes in environmental samples. First of all, analysis result showed that tritium released from PHWR was more than ten times as gas and double to three times as liquid in comparison to PWR in 2013. Independent release management in NPP units is needed to precisely control and analyze tritium, since there were 2 units of some NPPs having the same amount of release during analysis. In analysis on frequency of wind direction, average range showed 1.7 to 11.5% by 16-point compass. In case of analysis on sampling points by wind direction, Result showed most of the sampling points are right in places. However, There are some areas needed to examine. In analysis on tritium concentration changes in environmental samples, tritium concentration near NPPs was higher than one far away from NPPs. In case of environmental samples far from PWR, a trace of tritium occur. While, tritium concentration near NPPs was more than or equal to one further from PHWR. In conclusion, tritium occurs considerably in PHWR and is lower than standard in samples. but, it is still detected. Therefore, it is needed to strengthen control in system in NPPs and to consistently monitor tritium in environment.

• Proceedings of the Korean Nuclear Society Conference
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• 1998.05b
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• pp.369-376
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• 1998

원자로 압력용기는 원자력발전소의 일차 압력경계를 구성하는 핵심 부품으로 이의 건전성은 원전의 안전성과 수명관리에 결정적인 영향을 미친다. 탄소강으로 구성된 압력용기는 노심에 근접하게 위치하여 운전중 계속되는 고속중성자 조사로 인하여 인성이 감소한다. 운전중 비상노심 냉각수가 주입되어 압력용기가 급격하게 냉각되면서 압력이 높게 유지되거나 재가압이 되는 가압열충격 현상이 발생하는 경우 조사취화된 압력용기가 적절한 안전여유를 가지지 못할 수도 있다. USNRC에서는 이에 대한 종합적인 연구결과를 바탕으로 가압열충격 규정을 제정하여 가압열충격 기준온도(RT$_{PTS}$)의 계산 방법과 심사기준온도를 제시하였다. 가압열충격 심사기준온도의 결정근거가 기술되어 있는 SECY 82-465에 의하면 축방향 용접부에 대한 위험도를 평가하여 270℉를 심사기준온도로 정하고 원주방향 용접부에 대해서는 30℉를 더하여 300℉를 심사기준온도로 제시하였다. 이 연구에서는 이렇게 제정된 원주방향 용접부에 대한 심사기준온도의 적정성을 평가하기 위하여 균열방향에 따른 가압열충격 위험도를 VISA-II 코드로 평가하였다. 우선 가압열충격 기준온도 제정 시 사용된 방법과 결과들을 검토하고 NRC의 계산결과를 재현하였다. 이를 바탕으로 원주방향 용접부에 대한 위험도를 평가한 결과 균열방향의 차이를 고려하기 위해 적용된 기술적 여유도인 30℉는 과도한 보수성을 내포하고 있음을 알 수 있었다. 원주방향 용접부가 축방향 용접부와 동일한 수준의 가압열충격 위험도를 가지기 위한 심사기준온도 차이는 50℉ 이상인 것으로 평가되었다.을 수 있었다.ngineering because this field has large uncertainties on predicting the effect of earthquake on structures. This paper is based on the presented paper at the Bertero Symposium held in January 31an4 February 1 at Berkeley, California, USA which was entitled "Needs to Evaluate Real Seismic Performance of Buildings-Lessons from 1995 Hyogoken-Nambu Earthquake-". The lessons for buildings from the damage due to the Hyogoken-Nambu Earthquake are necessity to develop more rational seismic design codes based upon a performance-based design concept, and to evaluate seismic performance of existing buildings. In my keynote lecture at the Korean Association for Computational Structural Engineering, the history of seismic design and use of structural analysis in Japan, the lessons for buildings from

• Proceedings of the Korean Nuclear Society Conference
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• 1995.10a
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• pp.97-102
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• 1995

벨기에, 독일 및 프랑스를 비롯한 유럽의 여러 나라와 일본은 플루토늄을 혼합핵연료로 만들어 경수로에 부분적으로 장전하여 재순환시키는 방법에 대한 연구를 오래전부터 계속하여 현재는 이를 상용화하는 단계까지 왔다. 이전의 혼합핵연료의 경수로에의 이용이 핵연료 자원을 효과적으로 이용하는 측면이 중시되었으나, 최근에는 잉여 플루토늄 처리 및 혼합핵연료의 사용을 일부 원자로에 국한하는 목적으로 혼합핵연료를 노심 전체에 장전하여 사용하는 연구가 진행되고 있다. 따라서 본 논문에서는 혼합핵연료를 가압경수로 노심 전체에 장전하는 개념에 대하여 플루토늄의 소모 및 노심의 핵특성 관점에서 검토하였다. 그 결과 기존의 가압경수로에 혼합핵연료로 전노심을 구성하여 연소시킬 경우 fissile 플루토늄 원소의 초기 장전량이 방출시에는 약 60% 수준으로, 플루토늄의 총량은 약 70% 수준으로 감소하고 있다. 기존의 경수로에 혼합핵연료를 전체적으로 장전하면 900 ㎿급 원자로 1기당 년간 약 1톤가량의 플루토늄이 소요되며, 이를 실현하기 위해서는 제어봉 계통의 추가 설치 및 붕산계통의 고붕산화 등의 설비의 변경과 핵특성 변화에 따른 안전성 분석 등이 필요할 것이다.

• Proceedings of the Korean Society of Propulsion Engineers Conference
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• 2006.11a
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• pp.122-126
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• 2006

Two types of pressurization system and low weight feeding piping system are developed. With sub-system tests, ullage pressure control performance was verified for 1 step and 2 step pressurization system and the feeding performance of feeding piping system was also verified. The weight of the feeding piping system is low enough for the application of launch vehicle. In addition, LOX conditioning system is developed for avoiding geysering and LOX temperature rise. Integrated performance was verified through integrated on-board feeding system performance tests.

• Food Science and Preservation
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• v.20 no.6
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• pp.784-790
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• 2013

The quality characteristics of Campbell grape juice with different extraction processes (AE; autoclave extraction, HWE: hot water extraction, and EE: enzyme extraction) were investigated. The juice yields of the AE, HWE, and EE juices were 79.8%, 82.3% and 92.6%, respectively. The titratable acidity and soluble solids of the EE juice were significantly higher than those of the other extracts. There was no significant difference in the $L^*$ values of the juices, but the $a^*$ and $b^*$ values of the EE juice were higher than those of the other extracts. The viscosity of the HWE and EE juices was higher than that of the AE juice. The major free sugars in the grape juice were identified as glucose and fructose, and the highest organic acid content was found in the EE juice. The total polyphenol content of the EE juice was 55.7 mg% and was higher than those of the AE and HWE juices, which were 31.3 mg% and 39.5 mg%, respectively. Especially, the anthocyanin content of the EE juice was 22.1 mg%, which was two to four times higher than those of the AE and HWE juices, which were 4.5 mg% and 10.5 mg%, respectively. The EE juice showed the highest antioxidant effect, measured from the DPPH free radical scavenging activity and reducing power. In conclusion, we suggest that the enzyme treatment in the grape extraction was more effective than the autoclave and hot water methods.

• Journal of the Computational Structural Engineering Institute of Korea
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• v.24 no.4
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• pp.449-455
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• 2011

Recently, international collaborative research which was organized at Bhabha Atomic Research Centre in India, was conducted to develop for pressure capacity and nonlinear behavior of PHWR 1/4 scale nuclear containment building between experimental test and numerical code. In this paper, a nonlinear finite element analysis was carried out in order to predict ultimate pressure capacity and nonlinear behavior of the 1/4 scale containment building. The 1/4 scale containment building is consisted of basemat, cylinder wall, dome and 4-buttress. For the finite element analysis, commercial program ABAQUS was used. Finite element models including concrete, rebar and tendon have been developed for assessment of ultimate pressure capacity and failure mode for nuclear containment building. From the analysis results, first crack of the concrete, the yielding of the rebar and ultimate capacity pressure occurred at $1.6P_d$(design pressure), $3.36P_d$ and $4.0P_d$, respectively.

• Restorative Dentistry and Endodontics
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• v.31 no.1
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• pp.66-71
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• 2006

To evaluate the ratio of gutta-percha area in the canal after canal obturation with Continuous Wave of Condensation Technique (CWCT) with varying depths of plugger penetration, forty root canals of extracted human teeth were prepared up to size 40 of 0.06 taper with $ProFile^{(R)}$. Canals of three groups were filled with CWCT with System $B^{TM}$ (Analytic Tech. , USA) and different plugger penetration depths of 3, 5, or 7 mm from the apex. Canals of one group were filled with lateral condensation technique as a control The felled teeth were cross-sectioned at 1, 2 and 3 mm levels from the apical foramen. The ratio of gutta-percha area in the canal was analyzed using $Auto^{(R)}$ Cad 2000. Data were analyzed with one-way ANOVA and Duncan's multiple range test. At all levels, higher gutta-percha area ratio was found with deeper plugger penetration depth in CWCT, and cold lateral condensation group showed higher ratio than group of plugger penetration to apical 7 mm in CWCT. At apical 1 mm and 2 mm levels, group of plugger penetration to apical 3 mm showed significantly high or gutta-percha area ratio than those of apical 7 mm and lateral condensation (p<0.05). It is concluded therefore that, under the conditions of the present study, deeper plugger penetration depth results in more favorable and efficient obturation in CWCT.

• Journal of the Korean Recycled Construction Resources Institute
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• v.11 no.4
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• pp.542-551
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• 2023

In this paper, the thermal properties of porous concrete containing natural fine aggregates in bottom ash aggregates were analyzed. In this study, natural fine aggregates were used for bottom ash aggregates to understand the material properties of each aggregate and then used as an aggregate for porous concrete. A porous concrete specimen was manufactured by fixing the water-binder ratio at 0.25 and designating the compaction at 0.5, 1.5, and 2.5 MPa. Unit weight, total void ratio and thermal conductivity test were measured and discussed. As the compaction increased and the mixing ratio of natural fine aggregates increased, the unit weight and thermal conductivity increased, and the total void ratio decreased. In addition, the correlations between unit weight, total void ratio and thermal conductivity of porous concrete with previous experimental data were presented and the correlation coefficient (R²) was also analyzed.

• Proceedings of the Korean Society of Propulsion Engineers Conference
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• 1998.04a
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• pp.31-31
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• 1998

위성체의 보조추진시스템은 임구궤도까지의 궤도진입 및 임무궤도상에서의 속도 또는 자세제어에 필요한 임펄스를 제공한다. 단일하이드라진 추력기는 하이드라진(H$_2$H$_4$)과 자발적 촉매(Shell 405)의 발열 및 흡열 열분해 반응에 의해 발생하는 질소($N_2$), 수소(H$_2$), 암모니아(NH$_3$), 혼합가스를 노즐을 통해 방출하므로써 요구되는 impulse를 얻는다. 단일하이드라진 추력기 설계는 주입기, 촉매대, 노즐과 기타 설계 형태에 따른 다지관, 링, 스크린, 지지판 등의 부수적인 부품으로 구성된다. 추력기 제작 과정은 크게 piece-parts 기계가공, HEA(Head End Assembly)와 TCA(Thrust Chamber Assembly)로 구성되고 각 세부공정마다 전수시험 및 검사를 가진다. 연소시험설비는 최소 모사진 공 수준이 고도 100,000 ft(8.4 torr)를 만족시킬 수 있는 진공설비, 시험제어부, 성능변수 측정 및 처리부, 추진제 가압 공급부, 기타 환경 안전 및 부대 설비로 구성된다. 추력기 연소성능시험 절차는 추진제 충전 및 오염 여부 표본 검사, 가압 및 공급 라인 이상여부 확인, 추력기 장착, 추진제 가압 및 공급, 시험장치 보정, 진공 모사 및 연소성능시험, data 처리 등으로 구성된다.