• 제목/요약/키워드: open reactor

검색결과 136건 처리시간 0.028초

Extension of the NEAMS workbench to parallel sensitivity and uncertainty analysis of thermal hydraulic parameters using Dakota and Nek5000

  • Delchini, Marc-Olivier G.;Swiler, Laura P.;Lefebvre, Robert A.
    • Nuclear Engineering and Technology
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    • 제53권10호
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    • pp.3449-3459
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    • 2021
  • With the increasing availability of high-performance computing (HPC) platforms, uncertainty quantification (UQ) and sensitivity analyses (SA) can be efficiently leveraged to optimize design parameters of complex engineering problems using modeling and simulation tools. The workflow involved in such studies heavily relies on HPC resources and hence requires pre-processing and post-processing capabilities of large amounts of data along with remote submission capabilities. The NEAMS Workbench addresses all aspects of the workflows involved in these studies by relying on a user-friendly graphical user interface and a python application program interface. This paper highlights the NEAMS Workbench capabilities by presenting a semiautomated coupling scheme between Dakota and any given package integrated with the NEAMS Workbench, yielding a simplified workflow for users. This new capability is demonstrated by running a SA of a turbulent flow in a pipe using the open-source Nek5000 CFD code. A total of 54 jobs were run on a HPC platform using the remote capabilities of the NEAMS Workbench. The results demonstrate that the semiautomated coupling scheme involving Dakota can be efficiently used for UQ and SA while keeping scripting tasks to a minimum for users. All input and output files used in this work are available in https://code.ornl.gov/neams-workbench/dakota-nek5000-study.

Removing nitrogenous compounds from landfill leachate using electrochemical techniques

  • Nanayakkara, Nadeeshani;Koralage, Asanga;Meegoda, Charuka;Kariyawasam, Supun
    • Environmental Engineering Research
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    • 제24권2호
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    • pp.339-346
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    • 2019
  • In this research, applicability of electrochemical technology in removing nitrogenous compounds from solid waste landfill leachate was examined. Novel cathode material was developed at laboratory by introducing a Cu layer on Al substrate (Cu/Al). Al and mild steel (MS) anodes were investigated for the efficiency in removing nitrogenous compounds from actual leachate samples collected from two open dump sites. Al anode showed better performances due to the effect of better electrocoagulation at Al surface compared to that at MS anode surface. Efficiency studies were carried out at a current density of $20mA/cm^2$ and at reaction duration of 6 h. Efficiency of removing nitrate-N using Al anode and developed Cu/Al cathode was around 90%. However, for raw leachate, total nitrogen (TN) removal efficiency was only around 30%. This is due to low ammonium-N removal as a result of low oxidation ability of Al. In addition to the removal of nitrogenous compounds, reactor showed about 30% removal of total organic carbon. Subsequently, raw leachate was diluted four times, to simulate pre-treated leachate. The diluted leachate was treated and around 88% removal of TN was achieved. Therefore, it can be said that the reactor would be good as a secondary or tertiary treatment step in a leachate treatment plant.

Influence of nuclear data library on neutronics benchmark of China experimental fast reactor start-up tests

  • Guo, Hui;Jin, Xin;Huo, Xingkai;Gu, Hanyang;Wu, Haicheng
    • Nuclear Engineering and Technology
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    • 제54권10호
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    • pp.3888-3896
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    • 2022
  • Nuclear data is the basis of reactor physics analysis. This paper aim at studying the influence of major evaluated nuclear data libraries, CENDL-3.2, ENDF/B-VIII.0, JEFF-3.3, and JENDL-4.0u, on the neutronics modelling of CEFR start-up tests. Results show these four libraries have a good performance and consistency in the modelling CEFR start-up tests. The JEFF-3.3 results exhibit only an 8 pcm keff difference with the measurement. The difference in criticality is decomposed by nuclide, which shows the large overestimation of CENDL-3.2 is mainly from the cross-section of 52Cr. Except for few cases, the calculation results are within 1σ of measurement uncertainty in control rod worth, sodium void reactivity, temperature reactivity, and subassembly swap reactivity. In the evaluation of axial and radial reaction distribution, there are about 65% of relative errors that are less than 5% and 82% of relative errors that are less than 10%.

Feasibility and performance limitations of Supercritical carbon dioxide direct-cycle micro modular reactors in primary frequency control scenarios

  • Seongmin Son;Jeong Ik Lee
    • Nuclear Engineering and Technology
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    • 제56권4호
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    • pp.1254-1266
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    • 2024
  • This study investigates the application of supercritical carbon dioxide (S-CO2) direct-cycle micro modular reactors (MMRs) in primary frequency control (PFC), which is a scenario characterized by significant load fluctuations that has received less attention compared to secondary load-following. Using a modified GAMMA + code and a deep neural network-based turbomachinery off-design model, the authors conducted an analysis to assess the behavior of the reactor core and fluid system under different PFC scenarios. The results indicate that the acceptable range for sudden relative electricity output (REO) fluctuations is approximately 20%p which aligns with the performance of combined-cycle gas turbines (CCGTs) and open-cycle gas turbines (OCGTs). In S-CO2 direct-cycle MMRs, the control of the core operates passively within the operational range by managing coolant density through inventory control. However, when PFC exceeds 35%p, system control failure is observed, suggesting the need for improved control strategies. These findings affirm the potential of S-CO2 direct-cycle MMRs in PFC operations, representing an advancement in the management of grid fluctuations while ensuring reliable and carbon-free power generation.

하나로 2차 냉각탑의 냉각팬 감속기의 진동분석 (Vibration Analysis of a Cooling Fan Gear Reducer of the Secondary Cooling Tower in HANARO)

  • 박용철
    • 대한기계학회논문집A
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    • 제34권7호
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    • pp.935-941
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    • 2010
  • 하나로는 한국에 설치되어 있는 열출력 30MW의 개방 수조형 연구로 이다. 이는 발전로와 달리 원자로에서 발생하는 열을 이용하여 전기를 생산하는 것 대신에 원자로의 노심 온도를 유지하기 위하여 냉각탑을 통해 대기로 이 열을 냉각한다. 냉각탑 월간 점검 중에 냉각탑 4번의 냉각팬 감속기가 기준을 상회하는 고진동을 기록하였다. 본 연구의 목적은 고진동의 원인을 찾아 정상적으로 수리하기 위함이다. 연구 방법은 FFT 스펙트럼 기법을 적용하여 고진동의 원인을 분석하였다. 그 결과 고진동 주파수는 피니언 기어의 고유 진동수의 두 배인 354Hz이었다. 피니언 기어를 점검한 결과 이빨 표면이 깨져 있었다. 깨진 피니언 기어를 제거하고 새것으로 교체한 후에는 감속기는 정상적으로 작동하였다.

Symmetric Multi-Processing 시스템에서 다양한 병렬 기법 모델을 적용한 병렬 CUPID 코드의 성능분석 (Performance Analysis of the Parallel CUPID Code for Various Parallel Programming Models in Symmetric Multi-Processing System)

  • 전병진;이재룡;윤한영;최형권
    • 대한기계학회논문집B
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    • 제38권1호
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    • pp.71-79
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    • 2014
  • 본 연구에서는 가압경수로 주요 기기의 고정밀 열수력 해석을 위한 CUPID(Component Unstructured Program for Interfacial Dynamics) 코드의 압력장 해석을 위한 이중공액구배법(Bi-Conjugate Gradient) 알고리즘의 병렬화를 SMP(Symmetric Multi Processing) 시스템에서 고찰한다. 비압축성 후향계단 유동문제의 병렬해석을 다양한 격자 조밀도를 가지는 격자들에 대하여 세 가지 대표적인 병렬 기법(MPI, OpenMP, 하이브리드)을 적용하여 병렬성능 비교를 수행하였다. 병렬처리 성능은 해석 문제의 크기뿐만 아니라 캐쉬 메모리 크기에도 영향을 받으므로, 전체 계산량이 매우 적거나 개별 쓰레드에 사용되는 메모리가 캐쉬 메모리보다 매우 큰 경우에는 병렬화에 의한 성능 향상이 낮음을 확인하였다. 또한, 문제 크기에 상관없이 MPI 기법이 OpenMP보다 성능이 우수했으며, 상대적으로 적은 쓰레드를 사용한 경우엔 하이브리드 기법이 가장 우수한 성능을 보였다.

Containment Closure Time Following the Loss of Shutdown Cooling Event of YGN Units 3&4

  • Seul, Kwang-Won;Bang, Young-Seok;Kim, Hho-Jung
    • Nuclear Engineering and Technology
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    • 제31권1호
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    • pp.68-79
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    • 1999
  • The YGN Units 3&4 plant conditions during shutdown operation were reviewed to identify the possible event scenarios following the loss of shutdown cooling (SDC) event. For the five cases of typical reactor coolant system (RCS) configurations under the worst event sequence, such as unavailable secondary cooling and no RCS inventory makeup, the thermal hydraulic analyses were performed using the RELAP5/MOD3.2 code to investigate the plant behavior following the event. The thermal hydraulic analyses include the estimation of time to boil, time to core uncovery, and time to core heat up to determine the containment closure time to prevent the uncontrolled release of fission products to atmosphere. The result indicates that the containment closure is recommended to be achieved within 42 minutes after the loss of SDC for the steam generator (SG) inlet plenum manway open case or the large cold leg open case under the worst event sequence. The containment closure time is significantly dependent on the elevation and size of the opening and the SG secondary water level condition. It is also found that the containment closure needs to be initiated before the boiling time to ensure the survivability of the workers in the containment. These results will provide useful information to operators to cope with the loss of SDC event.

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Numerical study on conjugate heat transfer in a liquid-metal-cooled pipe based on a four-equation turbulent heat transfer model

  • Xian-Wen Li;Xing-Kang Su;Long Gu;Xiang-Yang Wang;Da-Jun Fan
    • Nuclear Engineering and Technology
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    • 제55권5호
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    • pp.1802-1813
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    • 2023
  • Conjugate heat transfer between liquid metal and solid is a common phenomenon in a liquid-metal-cooled fast reactor's fuel assembly and heat exchanger, dramatically affecting the reactor's safety and economy. Therefore, comprehensively studying the sophisticated conjugate heat transfer in a liquid-metal-cooled fast reactor is profound. However, it has been evidenced that the traditional Simple Gradient Diffusion Hypothesis (SGDH), assuming a constant turbulent Prandtl number (Prt,, usually 0.85 - 1.0), is inappropriate in the Computational Fluid Dynamics (CFD) simulations of liquid metal. In recent decades, numerous studies have been performed on the four-equation model, which is expected to improve the precision of liquid metal's CFD simulations but has not been introduced into the conjugate heat transfer calculation between liquid metal and solid. Consequently, a four-equation model, consisting of the Abe k - ε turbulence model and the Manservisi k𝜃 - ε𝜃 heat transfer model, is applied to study the conjugate heat transfer concerning liquid metal in the present work. To verify the numerical validity of the four-equation model used in the conjugate heat transfer simulations, we reproduce Johnson's experiments of the liquid lead-bismuth-cooled turbulent pipe flow using the four-equation model and the traditional SGDH model. The simulation results obtained with different models are compared with the available experimental data, revealing that the relative errors of the local Nusselt number and mean heat transfer coefficient obtained with the four-equation model are considerably reduced compared with the SGDH model. Then, the thermal-hydraulic characteristics of liquid metal turbulent pipe flow obtained with the four-equation model are analyzed. Moreover, the impact of the turbulence model used in the four-equation model on overall simulation performance is investigated. At last, the effectiveness of the four-equation model in the CFD simulations of liquid sodium conjugate heat transfer is assessed. This paper mainly proves that it is feasible to use the four-equation model in the study of liquid metal conjugate heat transfer and provides a reference for the research of conjugate heat transfer in a liquid-metal-cooled fast reactor.

미생물 연료전지의 원리 및 환경보건 분야로의 응용 (Microbial Fuel Cells: Principles and Applications to Environmental Health)

  • 한선기
    • 한국환경보건학회지
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    • 제38권2호
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    • pp.83-94
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    • 2012
  • The research on microbial fuel cells (MFCs) needs various knowledge of different fields such as electrochemistry, microbiology, environmental engineering, and material engineering. Although electrochemically active bacteria are very diverse, the performance of MFCs is affected primarily by the structure of the reactor system. Thus, the development in the system architecture is critical to lower internal resistance and increase power generation for commercialization. This paper summarizes the principles of MFCs and demonstrates the infinite potential of MFCs in various applications including wastewater treatment, biosensors, biohydrogen production, remote power sources, implantable medical devices, etc.

Closed-Loop Timing Controller Design for Control Rod Drive Mechanism (CRDM) Control System in Pressurized Water Reactor

  • Kim, Byeong-Moon;Joon Lyou
    • Nuclear Engineering and Technology
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    • 제29권2호
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    • pp.167-174
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    • 1997
  • The method that the operating condition of Control Rod Drive Mechanism (CRDM) can be monitored without mounting sensors within CRDM housing was developed, and by using this developed method the closed-loop controller for the CRDM was designed which can optimize the performance and maximize the reliability of CRDM operation. Neural network is utilized as pattern recognition engine in detecting CRDM actuation. In this paper, most problems in previous open loop system are resolved. The control algorithms for closed-loop system ore developed and implemented within the hardware of timing controller based on microprocessor. All functions in the timing controller ore verified by means of real time CRDM simulator. The results show that the timing controller performs its intended functions properly.

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