• 에너지공학
• /
• 제25권1호
• /
• pp.185-191
• /
• 2016

피동충수용 혼합형 안전주입탱크는 한국원자력연구원에서 제안한 원자력 피동안전계통의 한 종류로, 안전주입탱크의 상부와 가압기를 연결하여 모든 운전압력 조건에서 냉각수 주입이 가능하도록 개선한 시스템이다. 본 연구에서는 피동충수용 혼합형 안전주입탱크, 가압기와 원자력압력용기에 대한 압력 네트워크를 통해 피동충수용 혼합형 안전주입탱크와 가압기의 압력이 평형이 되는 조건을 이론적으로 도출하였으며, 개별효과시험장치를 이용하여 안전주입탱크에서 발생하는 다양한 열수력 현상(증기응축 및 열혼합 현상)들을 파악하였다.

• Nuclear Engineering and Technology
• /
• 제14권3호
• /
• pp.122-137
• /
• 1982

고리 1호기 일부 반응도사고에 대한 민감도 분석을 수행하였다. 본 민감도 분석에 고려한 반응도 사고는 비교적 진행속도가 빠른 사고로서 미임계나 저출력 시동조건에서 발생한 제어뱅크 인출사고와 제어봉 일출사고가 이에 속한다. 본 분석작업은 다음과 같이 세단계로 수행하는 바 원자로 평균출력의 변동 계산과 최고점에서의 열전달계산 그리고 DNBR계산 단계로 나눌 수 있다. 계산에 사용된 전산코드들은 본 분석을 위하여 개발하거나 기존 전산코드들을 수정ㆍ보완하여 제작하였으며 신뢰도도 평가하였다. 원자로 설계 및 운전변수들이 사고발생시 원자로의 거동에 미치는 영향을 조사하기 위하여 민감도 분석을 수행하였다. 본 민감도 분석 결과에 근거하여 고리 1호기 반응도사고 분석에 사용된 최종안전분석보고서의 가정과 초기조건이 타당한가를 조사하였고, 또한 계산 결과도 보수적이고 신뢰할 수 있는지 판별하였다. 고리 1호기 반응도사고 분석에 사용된 가정 및 초기조건을 재검토하고 민감도를 분석한 결과 최종안전분석보고서의 해석결과는 보수적이고 신뢰 할 수 있는 것으로 평가되었다.

• Membrane and Water Treatment
• /
• 제11권1호
• /
• pp.79-85
• /
• 2020

A single-stage deammonification with a sequencing batch reactor (SBR) that simultaneous nitritation, anaerobic ammonia oxidation (anammox), and denitrification (SNAD) occur in one reactor has been widely applied for sidestream of wastewater treatment plant. For the stable and well-balanced SNAD, a feeding strategy of influent wastewater is one of the most important operating factors in the single-stage deammonification SBR. In this study, single-stage deammonification SBR (working volume 30L) was operated to treat a high-strength ammonium wastewater (1200 mg NH₄⁺-N/L) with different feeding strategies (single feeding and nine-step feeding) under the condition without COD. Each cycle of the step feeding involved 6 sub-cycles consisted of aerobic and anoxic periods for partial nitritation (PN) and anammox, respectively. Contrary to unstable performance in the single feeding, the step feeding showed better deammonification performance (0.565 kg-N/m³/day). Under the condition with COD, however, the nitrogen removal rate (NRR) decreased to 0.403 kg-N/m³/day when the Nine-step feeding strategies had an additional denitrification period before sub-cycles for PN and anammox. The NRR was recovered to 0.518 kg-N/m³/day by introducing an enhanced multiple-step feeding strategy. The strategy had 50 cycles consisted of feed, denitrification, PN, and anammox, instead of repeated sub-cycles for PN and anammox. The multiple-step feeding strategy without sub-cycle showed the most stable and excellent deammonification performance: high nitrogen removal efficiency (98.6%), COD removal rate (0.131 kg-COD/m³/day), and COD removal efficiency (78.8%). This seemed to be caused by that the elimination of the sub-cycles might reduce COD oxidation during aerobic condition but increase the COD utilization for denitrification period. In addition, among various sensor values, the ORP pattern appeared to be applicable to monitor and control each reaction step for deammonification in the multiple-step feeding strategy without sub-cycle. Further study to optimize the number of multiple-step feeding is still needed but these results show that the multiple-step feeding strategy can contribute to a well-balanced SNAD for deammonification when treating high-strength ammonium wastewater with COD in the single-stage deammonification SBR.

• 한국지반환경공학회 논문집
• /
• 제9권3호
• /
• pp.35-43
• /
• 2008

본 연구는 소규모 하수고도처리시설에 대해 변형 연속회분식공정을 적용하여 그 효용성을 평가하였다. 변형 연속회분식공정은 단일 반응조 내에서 유기물질 및 질소, 인 등이 제거되며 유입수의 유량 및 수질특성에 의해 적합한 운전방식을 선택할 수 있다. 각 공정의 기능 향상을 위해 원수 유입조건의 제어, 간헐 폭기방식에 의한 무산소 및 호기조건의 적절한 분배 그리고 처리수와 잉여슬러지의 고액분리를 위한 처리수 배출장치의 적용으로 설계된 유량 및 수질에 비해 낮은 부하 조건임에도 1일 3Cycle 운전모드로써 안정적인 처리효율을 나타냈다. 평가결과 유기물질 제거효율은 BOD의 경우 평균 120.4mg/L에서 6.8mg/L로 94.4%, CODMn은 95.7mg/L에서 11.0mg/L로 88.5%의 처리효율을 나타냈다. T-N의 제거효율은 평균 32.2mg/L의 유입수 농도에 대해서 약 69.6%, T-P의 경우는 유입수 농도 4.65mg/L에 대해 73.6%의 처리효율을 나타냈다. 동절기 평균 T-N과 T- P의 처리효율은 58.8%, 68.5%로 약간 감소하였지만 안정적인 처리효율을 나타냈다. 1차 무산소 호기조건에서 BOD는 90%, T-N은 67% T-P는 46%정도로 제거되었으며 T-P는 2차 무산소 호기조건에서 약 70%정도 제거되었다. 따라서 유입수의 간헐유입과 무산소 호기조건의 적정한 분배에 의해 질산화, 탈질 및 인의 과잉섭취에 유기물이 적절히 이용된 것으로 평가되어 소규모 고도하수처리시설에 적합한 공정으로 판단된다.

• 한국방사성폐기물학회:학술대회논문집
• /
• 한국방사성폐기물학회 2004년도 Proceedings of the 4th Korea-China Joint Workshop on Nuclear Waste Management
• /
• pp.64-72
• /
• 2004

The dryer (ten per unit) are operating to remove tritium in PHWR(Pressurized Heavy Water Reactor). There are coming out heavy water adsorbent from operating the dryer (95 drums for ten year per unit) The amount of radioactivity of heavy water adsorbent almost exceed ninety times more than disposal limit-in-itself showed by The Ministry of Science and Technology. It has to be disposed whole radioactive waste products, however there are problems of increase at the expense of their permanent disposal. In this research, We have studied how to remove kinds of nuclear materials and amount of tritium with in heavy water adsorbent. As the result we could develop disposal equipment and apply it. D20 adsorbent have to contain below Gamma nuclide O.3Bq/g and tritium 100Bq/g "The Regulation for disposal of the radioactivity wastes" showed by The Ministry of Science and Technology. There fore. So as to remove amount of tritium and kinds of nuclear materials (DTO) we needed a equipment. Also we have studied how to remove effectively radioactivity with in Adsorbent. As cleaning heavy water adsorbent and drying on each condition (temperature for drying and hours for cleaning). Because there is something to return heavy water adsorbent by removing impurities within adsorbent when it is dried o high temperature. After operating, we have been applying this research to the way to dispose heavy water adsorbent. Through this we could reduce solid waste products and the expense of permanent disposal of radioactive waste products and also we could contribute nuclear power plant run safely. According to the result we could keep the best condition of radiation safety super vision and we could help people believe in safety with Radioactivity wastes control for harmony with Environment.

• 공업화학
• /
• 제20권4호
• /
• pp.423-429
• /
• 2009

본 연구의 목적은 바이오가스를 이용하여 고농도 수소 생산과 CO 제거가 가능한 글라이딩아크 플라즈마 개질 시스템의 개발이다. 이를 위하여 수성가스 전이반응기는 수증기 주입량 변화,촉매층 온도 변화에 대하여, 선택적 산화반응기는 촉매층 온도변화, 공기주입량에 대하여 실험을 진행하였다. 기준조건은 S/C 비 3, 촉매층 온도 $700^{\circ}C$, 전체가스량 16 L/min, 입력전력 2.4 kW, 바이오가스 구성비($CH_4$ : $CO_2$ ) 6 : 4이다. 이때의 실험결과는 HTS의 최적조건은 S/C비 3, 반응온도 $500^{\circ}C$, LTS의 최적조건은 S/C 비 2.9, 반응온도 $300^{\circ}C$이다. 또한 PROX I단의 최적조건은 각각 공기유입량 300 mL/min, $190^{\circ}C$, PROX II단의 최적조건은 공기유입량 200 mL/min, $190^{\circ}C$을 나타내었다. 반응기를 모두 지난 후의 합성가스는 $H_2$ 수율 55%, $CH_4$ 전환율 97%, $CO_2$ 전환율 97%, CO 선택도는 0%로 바이오가스를 개질하여 생성된 합성가스는 높은 수율을 나타내며, CO 선택도는 0%를 나타내었다.

• 한국소음진동공학회:학술대회논문집
• /
• 한국소음진동공학회 2004년도 춘계학술대회논문집
• /
• pp.125-130
• /
• 2004

The vibration and buckling characteristics of the capsule for fuel irradiation test are studied. The natural frequencies of the capsule in air and under water are obtained by modal testing and finite element(FE) analysis using ANSYS program, and accelerations with flow are measured to estimate the compatibility with the operation requirement of the HANARO reactor. The experimental fundamental frequency of the capsule in the x and z direction is 8.5Hz and 8.75Hz in air, and 7.5Hz and 7.75Hz under water, respectively. The maximum amplitude of accelerations under the normal operating condition is measured as 11.0m/s$^2$ that is within the allowable vibrational limit(18.99m/s$^2$) of the reactor structure. Also, the maximum displacement at 100% flow is calculated as 0.13mm which is not interference with other nearby structures. FE analysis results show that the natural frequencies are found to be similar to those of the modal testing when three supporting parts are considered as simply supported conditions. From the buckling analysis, when the loading tool is applied, the critical buckling load of the capsule is 233N.

• 대한기계학회:학술대회논문집
• /
• 대한기계학회 2000년도 추계학술대회논문집A
• /
• pp.286-291
• /
• 2000

The reactor pressure vessel is usually cladded with stainless steel to prevent corrosion and radiation embrittlement, and number of subclad cracks have been found during an in-service-inspection. Therefore assessment for subclad cracks should be made for normal operating conditions and faulted conditions such as PTS. Thus, in order to find the optimum fracture assessment procedures for subclad cracks under a pressurized thermal shock condition, in this paper, three different analyses were performed, ASME Sec. XI code analysis, an LEFM(Liner elastic fracture mechanics) analysis and an EPFM(Elastic plastic fracture mechanics) analysis. The stress intensity factor and the Maximum $RT_{NDT}$ were used for characterizing. Analysis based on ASME Sec. XI code does not completely consider the actual stress distribution of the crack surface, so the resulting Maximum allowable $RT_{NDTS}$ can be non-conservative, especially for deep cracks. LEFM analysis, which does not consider elastic-plastic behavior of the clad material, is much more non-conservative than EPFM analysis. Therefore, It is necessary to perform EPFM analysis for the assessment of subclad cracks under PTS.

• 한국물환경학회지
• /
• 제20권4호
• /
• pp.365-369
• /
• 2004

Submerged membrane bio-reactor equipped with a hollow fiber microfiltration was applied to reuse weaving wastewater of water jet loom, where two parameters such as the concentration of MLSS and the flux were controlled. While the flux at the concentration of MLSS around 900mg/L was constantly kept over 0.4m/d and 0.8m/d in a short time, the stable flux at around 300mg/L of MLSS was shown at the 8 days later. Regardless of MLSS and flux, BOD, CODcr and Turbidity of the permeate were 1~2mg/L, 7~10mg/L and below 1 NTU, which were 85~90%, 87~90% and 98% of removal efficiency, respectively. The stable operation without fouling was achieved because the contents of ECP were smaller than those of common MBR processes and the composition(saccharide/protein) was kept constantly. In this study, 0.5~1.0m/d of flux and 400~900mg/L of MLSS were considered as the most recommendable operating condition for the reuse of weaving wastewater.

• 한국소음진동공학회논문집
• /
• 제14권8호
• /
• pp.741-748
• /
• 2004

The vibration and buckling characteristics of the capsule for fuel irradiation test are studied. The natural frequencies of the capsule in air and under water are obtained by modal testing and finite element (FE) analysis using ANSYS program, and accelerations with flow are measured to estimate the compatibility with the operation requirement of the HANARO reactor. The experimental fundamental frequencies of the capsule in the x and z direction are 8.5 Hz and 8.75 Hz in air, and 7.5 Hz and 7.75 Hz under water, respectively. The maximum amplitude of accelerations under the normal operating condition is measured as 11.0 m/s$^2$ that is within the allowable vibrational limit(18.99 m/s$^2$) of the reactor structure. Also, the maximum displacement at 100％ flow is calculated as 0.13 mm which is not interference with other nearby structures. FE analysis results show that the natural frequencies are found to be similar to those of the modal testing when three supporting parts are considered as simply supported conditions. From the buckling analysis, when the loading tool is applied, the critical buckling load of the capsule is 233 N.