• 제목/요약/키워드: Single reactor

검색결과 398건 처리시간 0.028초

Unsteady Single-Phase Natural Circulation Flow Mixing Prediction Using CATHARE Three-Dimensional Capabilities

  • Salah, Anis Bousbia;Vlassenbroeck, Jacques
    • Nuclear Engineering and Technology
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    • 제49권3호
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    • pp.466-475
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    • 2017
  • Coolant mixing under natural circulation flow regime constitutes a key parameter that may play a role in the course of an accidental transient in a nuclear pressurized water reactor. This issue has motivated some experimental investigations carried out within the OECD/NEA PKL projects. The aim was to assess the coolant mixing phenomenon in the reactor pressure vessel downcomer and the core lower plenum under several asymmetric steady and unsteady flow conditions, and to provide experimental data for code validations. Former studies addressed the mixing phenomenon using, on the one hand, one-dimensional computational approaches with cross flows that are not fully validated under transient conditions and, on the other hand, expensive computational fluid dynamic tools that are not always justified for large-scale macroscopic phenomena. In the current framework, an unsteady coolant mixing experiment carried out in the Rossendorf coolant mixing test facility is simulated using the three-dimensional porous media capabilities of the thermal-hydraulic system CATHARE code. The current study allows highlighting the current capabilities of these codes and their suitability for reproducing the main phenomena occurring during asymmetric transient natural circulation mixing conditions.

Optimal design of passive containment cooling system for innovative PWR

  • Ha, Huiun;Lee, Sangwon;Kim, Hangon
    • Nuclear Engineering and Technology
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    • 제49권5호
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    • pp.941-952
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    • 2017
  • Using the Generation of Thermal-Hydraulic Information for Containments (GOTHIC) code, thermal-hydraulic phenomena that occur inside the containment have been investigated, along with the preliminary design of the passive containment cooling system (PCCS) of an innovative pressurized water reactor (PWR). A GOTHIC containment model was constructed with reference to the design data of the Advanced Power Reactor 1400, and report related PCCS. The effects of the design parameters were evaluated for passive containment cooling tank (PCCT) geometry, PCCS heat exchanger (PCCX) location, and surface area. The analyzed results, obtained using the single PCCT, showed that repressurization and reheating phenomena had occurred. To resolve these problems, a coupled PCCT concept was suggested and was found to continually decrease the containment pressure and temperature without repressurization and reheating. If the installation level of the PCCX is higher than that of the PCCT, it may affect the PCCS performance. Additionally, it was confirmed that various means of increasing the external surface area of the PCCX, such as fins, could help improve the energy removal performance of the PCCS. To improve the PCCS design and investigate its performance, further studies are needed.

Application of probabilistic safety assessment (PSA) to the power reactor innovative small module (PRISM)

  • Alrammah, Ibrahim
    • Nuclear Engineering and Technology
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    • 제54권9호
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    • pp.3324-3335
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    • 2022
  • Several countries show interest in the Generation-IV power reactor innovative small module (PRISM), including: Canada, Japan, Korea, Saudi Arabia and the United Kingdom. Generation IV International Forum (GIF) has recommended the utilizing of probabilistic safety assessment (PSA) in evaluating the safety of Generation-IV reactors. This paper reviews the PSA performed for PRISM using SAPHIRE 7.27 code. This work shows that the core damage frequency (CDF) of PRISM for a single module is estimated by 8.5E-8/year which is lower than the Generation-IV target that is 1E-6 core damage per year. The social risk of PRISM (likelihood of latent cancer fatality) with evacuation is estimated by 9.0E-12/year which is much lower than the basic safety objective (BSO) that is 1E-7/year. The social risk without evacuation is estimated by 1.2E- 11/year which is also much lower than the BSO. For the individual risk (likelihood of prompt fatality), it is concluded that it can be considered negligible with evacuation (1.0E-13/year). Assuming no evacuation, the individual risk is 2.7E-10/year which is again much lower than the BSO. In comparison with other PSAs performed for similar sodium fast reactors (SFRs), it shows that PRISM concept has the lowest CDF.

A Review of the Efficacy of Ultraviolet C Irradiation for Decontamination of Pathogenic and Spoilage Microorganisms in Fruit Juices

  • Ahmad Rois Mansur;Hyun Sung Lee;Chang Joo Lee
    • Journal of Microbiology and Biotechnology
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    • 제33권4호
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    • pp.419-429
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    • 2023
  • Ultraviolet C (UV-C, 200-280 nm) light has germicidal properties that inactivate a wide range of pathogenic and spoilage microorganisms. UV-C has been extensively studied as an alternative to thermal decontamination of fruit juices. Recent studies suggest that the efficacy of UV-C irradiation in reducing microorganisms in fruit juices is greatly dependent on the characteristics of the target microorganisms, juice matrices, and parameters of the UV-C treatment procedure, such as equipment and processing. Based on evidence from recent studies, this review describes how the characteristics of target microorganisms (e.g., type of microorganism/strain, acid adaptation, physiological states, single/composite inoculum, spore, etc.) and fruit juice matrices (e.g., UV absorbance, UV transmittance, turbidity, soluble solid content, pH, color, etc.) affect the efficacy of UV-C. We also discuss the influences on UV-C treatment efficacy of parameters, including UV-C light source, reactor conditions (e.g., continuous/batch, size, thickness, volume, diameter, outer case, configuration/arrangement), pumping/flow system conditions (e.g., sample flow rate and pattern, sample residence time, number of cycles), homogenization conditions (e.g., continuous flow/recirculation, stirring, mixing), and cleaning capability of the reactor. The collective facts indicate the immense potential of UV-C irradiation in the fruit juice industry. Existing drawbacks need to be addressed in future studies before the technique is applicable at the industrial scale.

Cross section generation for a conceptual horizontal, compact high temperature gas reactor

  • Junsu Kang;Volkan Seker;Andrew Ward;Daniel Jabaay;Brendan Kochunas;Thomas Downar
    • Nuclear Engineering and Technology
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    • 제56권3호
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    • pp.933-940
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    • 2024
  • A macroscopic cross section generation model was developed for the conceptual horizontal, compact high temperature gas reactor (HC-HTGR). Because there are many sources of spectral effects in the design and analysis of the core, conventional LWR methods have limitations for accurate simulation of the HC-HTGR using a neutron diffusion core neutronics simulator. Several super-cell model configurations were investigated to consider the spectral effect of neighboring cells. A new history variable was introduced for the existing library format to more accurately account for the history effect from neighboring nodes and reactivity control drums. The macroscopic cross section library was validated through comparison with cross sections generated using full core Monte Carlo models and single cell cross section for both 3D core steady-state problems and 2D and 3D depletion problems. Core calculations were then performed with the AGREE HTR neutronics and thermal-fluid core simulator using super-cell cross sections. With the new history variable, the super-cell cross sections were in good agreement with the full core cross sections even for problems with significant spectrum change during fuel shuffling and depletion.

가변형 간벽을 이용한 SBR 공정의 실증 Pilot 연구 (Positive Pilot Research of SBR Process with Flexible Vertical)

  • 김만수;박종운;박철휘
    • 대한환경공학회지
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    • 제27권4호
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    • pp.438-444
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    • 2005
  • 본 연구에서는 가변형 간벽을 설치하고 이 가변형 간벽의 열고 닫음에 따라 하나의 SBR 반응조를 시간적으로 뿐만 아니라 공간적으로도 분리시킴으로써 aerobic, anaerobic 또는 anoxic 상태의 구분을 명확히 하여 탈질 및 탈인 효율을 증대시켰다. 본 연구 결과 $COD_{Cr}$/N ratio 10($BOD_5$/N ratio 5) 정도의 실 플랜트 조건에서 T-N 및 T-P 제거효율은 90.9%와 75%를 나타내었다. 또한 잉여슬러지내 인 함유량 조사결과 기존 처리장에서 발생된 잉여슬러지의 인 함량비율을 100%라 할 때 pilot plant에서 발생된 잉여슬러지의 인 함유율은 생 슬러지의 경우 133.6%, 건조 슬러지의 경우 124.3%로서 기존 처리장의 슬러지내 인 함유율보다 $25{\sim}30%$ 정도 높은 것으로 조사되었다. 따라서 SBR반응조 내에 가변형 간벽을 설치함으로서 명확한 탈질 탈인을 위한 반응조건을 제시해 줄 수 있는 것으로 나타났다.

A comparative study on the impact of Gd2O3 burnable neutron absorber in UO2 and (U, Th)O2 fuels

  • Uguru, Edwin Humphrey;Sani, S.F.Abdul;Khandaker, Mayeen Uddin;Rabir, Mohamad Hairie;Karim, Julia Abdul
    • Nuclear Engineering and Technology
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    • 제52권6호
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    • pp.1099-1109
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    • 2020
  • The performance of gadolinium burnable absorber (GdBA) for reactivity control in UO2 and (U, Th)O2 fuels and its impact on spent fuel characteristics was performed. Five fuel assemblies: one without GdBA fuel rod and four each containing 16, 24, 34 and 44 GdBA fuel rods in both fuels were investigated. Reactivity swing in all the FAs with GdBA rods in UO2 fuel was higher than their counterparts with similar GdBA fuel rods in (U, Th)O2 fuel. The excess reactivity in all FAs with (U, Th)O2 fuel was higher than UO2 fuel. At the end of single discharge burn-up (~ 49.64 GWd/tHM), the excess reactivity of (U, Th) O2 fuel remained positive (16,000 pcm) while UO2 fuel shows a negative value (-6,000 pcm), which suggest a longer discharge burn-up in (U, Th)O2 fuel. The concentration of plutonium isotopes and minor actinides were significantly higher in UO2 fuel than in (U, Th)O2 fuel except for 236Np. However, the concentration of non-actinides (gadolinium and iodine isotopes) except for 135Xe were respectively smaller in (U, Th)O2 fuel than in UO2 fuel but may be two times higher in (U, Th)O2 fuel due to its potential longer discharge burn-up.

스마트 원자로냉각재펌프의 축소모형에 대한 수력성능 예측 (Prediction of Hydraulic Performance of a Scaled-Down Model of SMART Reactor Coolant Pump)

  • 권순국;박진석;유제용;이원재
    • 대한기계학회논문집A
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    • 제34권8호
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    • pp.1059-1065
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    • 2010
  • 본 연구에서는 SMART 원자로의 사류형 원자로냉각재펌프의 축소모형에 대한 수력성능을 예측하기 위하여 설계점을 포함한 다양한 탈설계점에서의 해석을 수행하였다. 계산시간의 효율성을 위하여 임펠러와 디퓨저 각 1개 유로로 이루어진 계산영역을 해석대상으로 선정하였다. 임펠러와 디퓨저간의 정보교환을 위하여 스테이지 기법을 사용하였다. 정상상태 비압축성 유동조건에서 축소모형의 수력성능특성을 파악하기 위하여 해석영역의 입구와 출구에서 압력차를 측정하여 양정, 효율과 축동력을 산출하였다. 수력성능 곡선은 일반적인 사류펌프의 성능특성을 잘 모사하는 것으로 나타났다. 저유량에서의 펌프 내부유동의 복잡한 흐름을 확인 하였다.

천연가스 열분해법에 의한 수소 및 탄소 제조 (Production of Hydrogen and Carbon Black Using Natural Gas Thermal Decomposition Method)

  • 장훈;이병권;임종성
    • 청정기술
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    • 제10권4호
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    • pp.203-213
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    • 2004
  • 천연가스의 열분해법은 천연가스 (CH4)를 고온에서 분해 시켜 수소와 탄소로 전환시키는 기술이다. 천연가스 열분해법의 가장 큰 장점은 이산화탄소의 발생 없이 수소와 탄소를 만드는 것이다. 본 연구에서는 이와같이 천연가스 고온 열분해법을 이용하여 메탄으로부터 수소와 탄소의 생성을 연구하였다. 실험을 통하여 메탄의 고온 열분해시 pyrocarbon이 반응관 내벽에 생성되며 그 위에 탄소가 퇴적되는 plugging 현상이 발생한다는 것을 알 수 있었다. 이 문제를 해결하기 위하여 본 연구에서는 이중관 반응기법, 반응 중간에 주기적으로 $O_2$$CO_2$로 퇴적된 탄소를 산화시키는 방법 등을 시도하였으며, 그 결과 어느 정도의 탄소 퇴적 현상을 해결할 수 있었다. 또한 SEM (Scanning Electron Microscope) image를 사용하여 탄소 입자의 크기를 측정하였으며 그 크기는 약 200 nm정도였다.

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간헐포기공정에서 포기/비포기 구간에 따른 질소제거 및 미생물 군집분석 (Nitrogen Removals according to Aeration/Non-aeration Periods in the Intermittent Aeration Reactor and Analysis of Microbial Community)

  • 최문수;이태진
    • 대한환경공학회지
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    • 제36권1호
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    • pp.42-48
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    • 2014
  • 본 연구에서는 단일반응조에서 포기/비포기 시간에 따른 하수 내 유기물질 및 질소화합물을 변화양상을 살펴보고자 하였다. 실험 결과 C/N비 3 : 1, 포기/비포기 20/40 min 구간에서부터 90% 이상의 안정적인 유기물 및 질소 제거가 이루어짐을 알 수 있었다. 포기/비포기 구간의 비율을 길게 유지하는 것이 탈질에 더욱 효과적이었으며 이는 비포기 구간을 유지하는 동안 반응조 내 미생물의 군집변화에 기인하는 것으로 판단하였다. PCR-DGGE를 한 결과, 유기물 및 질소화합물의 산화에 관여하는 미생물로 Dysgonomonas mossii strain Melo40, Eubacterium sp. oral clone JN088, Uncultured bacterium clone SPESB2_718과 Bacterium enrichment culture clone LE이 관찰되었고 탈질에 관여하는 미생물은 Uncultured Acidobacteria bacterium clone AKYG487, Lactobacillus harbinensis strain FQ003, Erythrobacter litoralis strain Gi-3, Phytobacter diazotrophicus strain Ls8, Mycobacterium sp. enrichment culture clone GE10037biofNNA로 나타났다.