• Title/Summary/Keyword: very high temperature reactor

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Prediction of the Tritium Behavior in Very High Temperature Gas Cooled Reactor Using TRITGO (TRITGO 코드를 이용한 초고온가스로 (VHTR) 삼중 수소 거동 예측)

  • Park, Jong-Hwa;Park, Ik-Kyu;Lee, Won-Jae
    • Journal of Radiation Protection and Research
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    • v.33 no.3
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    • pp.113-120
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    • 2008
  • In this study, The TRITGO code was introduced, which can predict the amount of tritium production, it's transport, removal, distribution and the level of contamination for the produced hydrogen by the tritium on the VHTR (very high temperature gas cooled reactor). The TRITGO code was improved so that the permeation to the IS Iodine Sulfide) loop for producing the hydrogen can be simulated. The contamination level of the produced hydrogen by the tritium was predicted by the improved code for the VHTR with 600MW thermal power. The contamination level for the produced hydrogen by tritium was predicted as 0.055 Bq/$H_2-g$. This level is three order of lower than the regulation value of 56 Bq/$H_2-g$ from Japan. From this study, the following results were obtained. it is important that the fuel coating (SiC layer) should be kept intact to prevent the tritium from releasing. Also it is necessary that the level of impurity such as 3He and Li in the helium coolant and the reflector consisting of the graphite should be kept as low as possible. It was found that the capacity of the purification system for filtering the impurities directly from the coolant will be the important design parameter.

High-Temperature Structural-Analysis Model of Process Heat Exchanger for Helium Gas Loop (I) (헬륨가스루프 시험용 공정열교환기에 대한 고온구조해석 모델링 (I))

  • Song, Kee-Nam;Lee, Heong-Yeon;Kim, Yong-Wan;Hong, Seong-Duk;Park, Hong-Yoon
    • Transactions of the Korean Society of Mechanical Engineers A
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    • v.34 no.9
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    • pp.1241-1248
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    • 2010
  • In large-scale production of hydrogen, a PHE (Process Heat Exchanger) is a key component because the heat required to carry out the Sulfur-Iodine chemical reaction that yields hydrogen is transferred from a VHTR (Very High Temperature Reactor) by the PHE. Korea Atomic Energy Research Institute established a helium gas loop for conducting performance test of components that are used in the VHTR. In this study, as a part of high-temperature structural-integrity evaluation of a designed PHE prototype that is scheduled to be tested in the helium gas loop, we carried out high-temperature structural-analysis modeling, thermal analysis, and thermal-expansion analysis for the designed PHE prototype. An appropriate constraint condition is proposed at the end of the in-flow and out-flow pipelines of the primary and secondary coolants and the proposed constraint condition will be applied to the design of the performance-test loop setup for the designed PHE prototype.

Macroscopic High-Temperature Structural Analysis Model for a Small-Scale PCHE Prototype (I) (소형 PCHE 에 대한 거시적 고온 구조 해석 모델링 (I))

  • Song, Kee-Nam;Lee, Heong-Yeon;Kim, Chan-Soo;Hong, Sung-Duk;Park, Hong-Yoon
    • Transactions of the Korean Society of Mechanical Engineers A
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    • v.35 no.11
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    • pp.1499-1506
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    • 2011
  • The IHX (intermediate heat exchanger) is a key component of nuclear hydrogen systems for the production of massive amounts hydrogen. The IHX transfers the $950^{\circ}C$ heat generated by the VHTR (very high temperature reactor) to a hydrogen production plant. The Korea Atomic Energy Research Institute established a small-scale gas loop to test the performance of key VHTR components and manufactured a small-scale PCHE (printed circuit heat exchanger) prototype, which is being considered as a candidate for the IHX, for testing in the small-scale gas loop. In this study, as a part of the high-temperature structural integrity evaluation of the small-scale PCHE prototype, we carried out high-temperature structural analysis modeling and macroscopic thermal and structural analysis for the small-scale PCHE prototype under the small-scale gas loop test conditions. This analysis serves as a precedent study to scheduled PCHE performance test in the small-scale gas loop. The results obtained in this study will be compared with the test results for the small-scale PCHE and then used to design the medium-scale PCHE prototype.

Long-Term Performance of Lab-Scale High Temperature Electrolysis(HTE) System for Hydrogen Production (Lab-scale 고온전기분해 수소생산시스템의 장기운전 성능평가)

  • Choi, Mi-Hwa;Choi, Jin-Hyeok;Lee, Tae-Hee;Yoo, Young-Sung;Koh, Jae-Hwa
    • Journal of Hydrogen and New Energy
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    • v.22 no.5
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    • pp.641-648
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    • 2011
  • KEPRI (KEPCO Research Institute) designed and operated the lab-scale high temperature electrolysis (HTE) system for hydrogen production with $10{\times}10cm^2$ 5-cell stack at $750^{\circ}C$. The electrolysis cell consists of Ni-YSZ steam/hydrogen electrode, YSZ electrolyte and LSCF based perovskite as air side electrode. The active area of one cell is 92.16 $cm^2$. The hydrogen production system was operated for 2664 hours and the performance of electrolysis stack was measured by means of current variation with from 6 A to 28 A. The maximum hydrogen production rate and current efficiency was 47.33 NL/hr and 80.90% at 28 A, respectively. As the applied current increased, hydrogen production rate, current efficiency and the degradation rate of stack were increased respectively. From the result of stack performance, optimum operation current of this system was 24 A, considering current efficiencies and cell degradations.

Performance test and uncertainty analysis of the FBG-based pressure transmitter for liquid metal system

  • Byeong-Yeon KIM;Jewhan LEE;Youngil CHO;Jaehyuk EOH;Hyungmo KIM
    • Nuclear Engineering and Technology
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    • v.54 no.12
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    • pp.4412-4421
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    • 2022
  • The pressure measurement in the high-temperature liquid metal system, such as Sodium-cooled Fast Reactor(SFR), is important and yet it is very challenging due to its nature. The measuring pressure is relatively at low range and the applied temperature varies in wide range. Moreover, the pressure transfer material in impulse line needs to considered the high temperature condition. The conventional diaphragm-based approach cannot be used for it is impossible to remove the effect of thermal expansion. In this paper, the Fiber Bragg Grating(FBG) sensor-based pressure measuring concept is suggested that it is free of problems induced by the thermal expansion. To verify this concept, a prototype was fabricated and tested in an appropriate conditions. The uncertainty analysis result of the experiment is also included. The final result of this study clearly showed that the FBG-based pressure transmitter system is applicable to the extreme environment, such as SFR and any other high-temperature liquid metal system and the measurement uncertainty is within reasonable range.

A Study of Hydrodenitrogenation of Quinoline Catalyzed by Sulfided $Ni-Mo/\gamma - Al_2O_3$ (황화 $Ni-Mo/\gamma - Al_2O_3$ 촉매상에서 Quinoline의 수소첨가탈질반응에 관한 연구)

  • 최응수;이원묵;김경림
    • Journal of Korean Society for Atmospheric Environment
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    • v.5 no.1
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    • pp.52-61
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    • 1989
  • The hydrodenitrogenation of quinoline dissolved in n-heptane was studied over sulfided Ni-Mo/$\gamma-Al_2O_3$ catalyst at the range of the temperature between 553 K and 673 and the total pressure between $20 \times 10^5$ Pa and $60 \times 10^5$ Pa in a fixed bed flow reactor. Quinoline conversion was very high at relatively low temperature and total pressure, and decreased with quinoline partial pressure. The thermodynamic equilibrium between quinoline and Py-THQ existed in wide ranges of experimental conditions and shifted in favor of quinoline at higher temperature. At the range of the temperature betwwen 553 K and 673 K and at the total pressure $60 \times 10^5$ Pa, the quinoline reaction rate was 1st order with respect to the concentr4ation of quinoline and its apparent activation energy was 7.15 Kcal/mole.

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Numerical analysis of the venturi flowmeter in the liquid lead-bismuth eutectic circuit after long-term operation

  • Zhichao Zhang;Rafael Macian-Juan;Xiang Wang
    • Nuclear Engineering and Technology
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    • v.56 no.3
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    • pp.1081-1090
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    • 2024
  • The liquid Lead-bismuth eutectic is used as the coolant for Gen-IV reactor concepts. However, due to its strong corrosive and high operating temperature, it is difficult to accurately measure the flow rate in long-term operating conditions. Venturi flowmeter is a simple structured flowmeter, which plays a very important role in the flow measurement of high-temperature liquid metals, especially since the existing flowmeters are difficult to be competent. It has the advantages of easy maintenance and stable operation. Therefore, it is necessary to study the operating conditions of the venturi flowmeter under high-temperature conditions. This work performs a series of simulations of the fluid-solid interaction between the flow liquid metal and venturi flowmeter with COMSOL software, including the dimensional sensitivity analysis of the venturi flowmeter to explore the most suitable structure and parameters for liquid heavy metal, the sensitivity analysis of the geometric parameters of the venturi tube on the varying conditions. It shows that when the contraction angle of the venturi flowmeter is 33°, the diffusion angle is 13°, the diameter of the throat is 8 mm, and the temperature of the lead-bismuth eutectic is 733.15 K, it is most suitable for the measurement in the lead-bismuth circuit.

A Study on the Temperature Characteristics of Main Coolant Pump for System-integrated Modular Advanced Reactor (SMART 원자로용 냉각재 순환펌프의 온도특성에 관한 연구)

  • Gu, Dae-Hyeon;Bang, Deok-Je;Gang, Do-Hyeon;Kim, Jong-In;Jo, Yun-Hyeon
    • The Transactions of the Korean Institute of Electrical Engineers B
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    • v.49 no.5
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    • pp.320-326
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    • 2000
  • The canned motor of 3-phase induction is used for main coolant pump(MCP). The type of motor is canned-motor that stator and rotor are welded by sealed can. So, cooling water flows in the air gap of the canned motor as an independent cycling cooling system from the air gap to yoke of the motor to prevent high temperature of stator can and to lubricate bearing. Heat exchange is occurred between cooling water in the air gap and cooling water from the exterior pump to prevent rising of temperature in the motor. I has to analyze the characteristics of can exactly because the loss and the heat in the can are very important to design MCP. Therefore, thermal analysis is studied considering the effect of eddy-current los induced in the can.

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Thermal Behavior of the Nuclear Graphite Waste Generated from the Decommissioning of the Nuclear Research Reactor (연구로 해체시 발생되는 흑연폐기물의 열적 거동)

  • 양희철;은희철;이동규;조용준;강영애;이근우;오원진
    • Proceedings of the Korean Radioactive Waste Society Conference
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    • 2004.06a
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    • pp.105-114
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    • 2004
  • This study investigated the thermal behavior of the nuclear graphite waste generated from the decommissioning of the Korean nuclear research reactor, The first part study investigated the decomposition rate of the nuclear graphite waste up to $1000^{\circ}C$ under various oxygen partial pressures using a thermo-gravimetric analyzer (TGA). Tested graphite waste sample not easily destroyed in the oxygen-deficient condition. However, the gas-solid oxidation reaction was found to be very effective in the presence of oxygen. No significant amount of the product of incomplete combustion was formed even in the limited oxygen concentration of 4% $O_2$. The influence of temperature and oxygen partial pressure was evaluated by the theoretical model analysis of the thermo-gravimetric data. The activation energy and the reaction order of graphite oxidation were evaluated as 128 kJ/mole and 1.1, respectively. The second part of this study investigated the behavior of radioactive elements under graphite oxidation atmosphere using thermodynamic equilibrium model. $^{22}Na$, $^{134}Cs$ and $^{137}Cs$ were found be the semi-volatile elements. Since volatile uranium species can be formulated at high temperatures above $1050^{\circ}C$, the temperature of incinerator furnace should be minimized. Other corrosion/activation products, fission products and uranium were found to be the non-volatile species.

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Study on the Relationship between Weather Conditions, Sewage and Operational Variables of WWTPs using Multivariate Statistical Methods (기상조건이 하수발생량 및 하수처리장 운전인자에 미치는 영향에 관한 통계적 분석)

  • Lee, Jae-Hyun
    • Journal of Korean Society on Water Environment
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    • v.28 no.2
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    • pp.285-291
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    • 2012
  • Generally, the rainfall and the influent of wastewater treatment plants (WWTPs) have strong relationship at the case of combined sewers. With the fact that the influent variations in terms of quantity and sewage quality is the most common and significant disturbance, the impact factor to the characteristics of sewage should be searched for. In this paper, the relationship between weather conditions such as humidity, temperature and rainfall and influent flowrate and contaminant concentration was analysed using factor analysis. Additionally, 3 influent types were deduced using cluster analysis and the distributions of operational variables were compared to the each groups by one-way ANOVA. The applied dataset were clustered to three groups that have the similar weather and influent conditions. These different conditions can cause the different operating conditions at WWTPs. That is, the Group 1 is for the condition with high humidity and rainfall, so DO concentration in the reactor was very high but MLSS concentration was very low because of too large flowrate. However, the Group 3 is classified to the case having low humidity, temperature, and rainfall, therefore, the SRT was the longest and the SVI was the highest due to the worst settleability in the winter for a year.