• 제목/요약/키워드: cooling channel

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Pressure Drop and Vibration Characteristics of the Capsule with the Modification of Bottom Structures (캡슐 하단부 구조변경에 따른 압력강하 및 진동특성)

  • Choi, M.H.;Choo, K.N.;Cho, M.S.;Kim, B.G.
    • Transactions of the Korean Society for Noise and Vibration Engineering
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    • v.15 no.12 s.105
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    • pp.1370-1377
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    • 2005
  • The bottom structure of an instrumented capsule is a part which is joined at the receptacle of the flow tube in the reactor in-core. A geometrical change of the bottom structure has an effect on the pressure drop and the vibration of the capsule. The out-pile test to evaluate the structural integrity of the material capsule called 04M-17U was performed by using a single channel and a half core test loop. From the pressure drop test, the optimized diameter of the cone shape's bottom structure which satisfies HANARO's flow requirement (19.6 kg/s) is 71 mm. The maximum displacement of the capsule measured at the half core test loop is lower than 1.0 mm. From the analysis results, it is found that the test hole will not be interfered with near the flow tubes because its displacement due to the cooling water is very small at 0.072 mm. The fundamental frequency of the capsule under water is 9.64 Hz. It is expected that the resonance between the capsule and the fluid flow due to the cooling water in HANARO's in-core will not occur. Also, the new bottom structure of a solid cone shape with 71 mm in diameter will be applicable to the material and special capsules in the future.

Analysis of Conjugated Heat Transfer for the Diffuser Exposed to Hot Combustion Gas (고온 연소가스에 노출되는 디퓨저의 복합 열전달량 계산)

  • Jin, Sang-Wook;Na, Jae-Jung;Rhe, Sang-Ho;Lee, Kyu-Jun;Lim, Jin-Shik;Kim, Sung-Don
    • Proceedings of the Korean Society of Propulsion Engineers Conference
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    • 2010.11a
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    • pp.231-234
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    • 2010
  • Analysis of conjugated heat transfer has been conducted for the diffuser exposed to hot combustion gas to design the mechanical durability in high temperature. All the heat transfer means, conduction, convection and radiation have been considered to calculate the total heat flux from hot gas to diffuser surface. The calculation has been implemented by two kinds of methods. One thing is one dimensional method based on empirical equations. The other is CFD(Computational Fluid Dynamics) axisymmetric calculation containing ${\kappa}-{\omega}$ SST(Shear Stress Transport) turbulent model and DO(Discrete Ordinate) radiation model. The derived results of two methods have compared and showed similar values. From this result, the amount of cooling water and the dimension of water cooling channel were decided.

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Thermal-hydraulic analysis of a new conceptual heat pipe cooled small nuclear reactor system

  • Wang, Chenglong;Sun, Hao;Tang, Simiao;Tian, Wenxi;Qiu, Suizheng;Su, Guanghui
    • Nuclear Engineering and Technology
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    • v.52 no.1
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    • pp.19-26
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    • 2020
  • Small nuclear reactor features higher power capacity, longer operation life than conventional power sources. It could be an ideal alternative of existing power source applied for special equipment for terrestrial or underwater missions. In this paper, a 25kWe heat pipe cooled reactor power source applied for multiple use is preliminary designed. Based on the design, a thermal-hydraulic analysis code for heat pipe cooled reactor is developed to analyze steady and transient performance of the designed nuclear reactor. For reactor design, UN fuel with 65% enrichment and potassium heat pipes are adopted in the reactor core. Tungsten and LiH are adopted as radiation shield on both sides of the reactor core. The reactor is controlled by 6 control drums with B4C neutron absorbers. Thermoelectric generator (TEG) converts fission heat into electricity. Cooling water removes waste heat out of the reactor. The thermal-hydraulic characteristics of heat pipes are simulated using thermal resistance network method. Thermal parameters of steady and transient conditions, such as the temperature distribution of every key components are obtained. Then the postulated reactor accidents for heat pipe cooled reactor, including power variation, single heat pipe failure and cooling channel blockage, are analyzed and evaluated. Results show that all the designed parameters satisfy the safety requirements. This work could provide reference to the design and application of the heat pipe cooled nuclear power source.

Pressure Drop and Vibration Characteristics of the Capsule with the Modification of Bottom Structures (캡슐 하단부 구조변경에 따른 압력강하 및 진동특성)

  • Choi, M.H.;Choo, K.N.;Cho, M.S.;Lee, K.H.;Kim, B.G.
    • Proceedings of the Korean Society for Noise and Vibration Engineering Conference
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    • 2005.11a
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    • pp.782-787
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    • 2005
  • The bottom structure of an instrumented capsule is a part which is joined at the receptacle of the flow tube in the reactor in-core. A geometrical change or the bottom structure has an effect on the pressure drop and the vibration of the capsule. The out-pile test to evaluate the structural Integrity of the material capsule called 04M-l7U was performed by using a single channel and a half core test loop. From the pressure drop test, the optimized diameter of the cone shape's bottom structure which satisfies HANARO's flow requirement (19 6 kg/s) is 71 mm. The maximum displacement of the capsule measured at the half core test loop is lower than 1.0 mm. From the analysis results, it is found that the test hole will not be interfered with near the flow tubes because its displacement due to the cooling water is very small at 0.072 mm. The fundamental frequency of the capsule under water is 9.64 Hz. It is expected that the resonance between the capsule and the fluid flow due to the cooling water in HANARO's In-core will not occur. Also, the new bottom structure of a solid cone shape with 71 mm in diameter will be applicable to the material and special capsules in the future.

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An Analysis on Performance Degradation of Silicon Photomultipliers over Temperatures Variation for PET-MR Application (PET-MR 시스템에 적용을 위한 실리콘 광증배센서의 온도 변화에 따른 성능 열화 분석)

  • Park, Kyeongjin;Kim, Hyoungtaek;Lim, Kyungtaek;Cho, Minsik;Kim, Giyoon;Cho, Gyuseong
    • Journal of Radiation Industry
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    • v.9 no.3
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    • pp.143-151
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    • 2015
  • A PET-MR system is particularly useful in diagnosing brain diseases. We have developed a prototype positron emission tomography (PET) system which can be inserted into the bore of a whole-body magnetic resonance imaging (MRI) system that enables us to obtain PET and MRI images simultaneously with a reduced cost. Silicon photomultipliers (SiPM) are appropriated as a PET detector at PET/MR system because detectors have a high gain and are insensitive to magnetic fields. Despite of its improved performance compared to that of PMT-based detectors, there is a problem of the photo-peak channel shift which is due to the increase of the temperature inside the ring detector. This problem will occur decreasing sensitivity of the PET and image distortion. In this paper, I quantitative analyze parameters of the KAIST SiPM depending on temperature by experiments. And I designed cooling methods in consideration of the degradation of sensors for correction of the temperature in the PET gantry. According to this research, we expect that distortive images and degradation of the sensitivity will not be occurred with using the above idea to reduce heat even if the PET system operates for a long time.

Prediction of the Flow Pattern Changes using FLOW-3D Model in the Effluent Region of the Samcheonpo Thermal Power Plant (TPP) (소수력 발전소 건설에 의한 삼천포 화력발전소 방류수로 흐름변화 예측)

  • Cho, Hong-Yeon;Jeong, Shin-Taek;Kim, Jeong-Dae;Kang, Kem-Seok
    • Journal of Korean Society of Coastal and Ocean Engineers
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    • v.18 no.4
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    • pp.338-347
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    • 2006
  • A small hydro-power plant using the seawater used as the cooling (circulated) water and discharged is under construction. The bigger size of the small hydro-power plant, the better in order to maximize the efficiency and the electric power. The optimal size, however, should be determined in the constraints of the channel un-disturbed range. The water level change should be checked in detail based on the hydraulic behaviour. In this study, the FLOW3D model, three-dimensional flow model, is setup using the flow measurement data in the effluent discharge channel and the flow pattern changes due to the small hydro-power plant construction are predicted by the model. The plant construction makes the increasing of the water level, and the water level in the upstream of the channel weir is increased 65 cm from 4.32 m to 4.97 m, in the condition of the design discharge $156m^3/s$ and the movable weir height of the hydro-power plant 3.8 m.

Development of liquid target for beam-target neutron source & two-channel prototype ITER vacuum ultraviolet spectrometer

  • Ahn, B.N.;Lee, Y.M.;Dang, J.J.;Hwang, Y.S.;Seon, C.R.;Lee, H.G.;Biel, W.;Barnsley, R.;Kim, D.E.;Kim, J.G.
    • Proceedings of the Korean Vacuum Society Conference
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    • 2011.02a
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    • pp.421-422
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    • 2011
  • The first part is about development of a liquid target for a neutron source, which is designed to overcome many of the limitations of traditional beam-target neutron generators by utilizing a liquid target neutron source. One of the most critical aspects of the beam-target neutron generator is the target integrity under the beam exposure. A liquid target can be a good solution to overcome damage to the target such as target erosion and depletion of hydrogen isotopes in the active layer, especially for the one operating at high neutron fluxes with no need for water cooling. There is no inherent target lifetime for the liquid target neutron generator when used with continuous refreshment of the target surface exposed to the energetic beam. In this work, liquid target containing hydrogen has been developed and tested in vacuum environment. Potentially, liquid targets could allow a point neutron source whose spatial extension is on the order of 1 to $10{\mu}m$. And the second is about the vacuum ultraviolet (VUV) spectrometer which is designed as a five-channel spectral system for ITER main plasma measurement. To develop and verify the design, a two-channel prototype system was fabricated with No. 3 (14.4 nm~31.8 nm) and No. 4 (29.0 nm~60.0 nm) among the five channels. For test of the prototype system, a hollow cathode lamp is used as a light source. The system is composed of a collimating mirror to collect the light from source to slit, and two holographic diffraction gratings with toroidal geometry to diffract and also to collimate the light from the common slit to detectors. The two gratings are positioned at different optical distances and heights as designed. To study the appropriate detector for ITER VUV system, two different electronic detectors of the back-illuminated charge coupled device and the micro-channel plate electron multiplier were installed and the performance has been investigated and compared in the same experimental conditions. The overall system performance was verified by measuring the spectrums.

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Silicon Oil-Based 2-Channel Fiber-Optic Temperature Sensor Using a Subtraction Method (감법을 이용한 실리콘 오일 기반의 2채널 광섬유 온도 센서)

  • Lee, Dong Eun;Yoo, Wook Jae;Shin, Sang Hun;Kim, Mingeon;Song, Young Beom;Kim, Hye Jin;Jang, Kyoung Won;Tack, Gye Rae;Lee, Bongsoo
    • Journal of Sensor Science and Technology
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    • v.25 no.5
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    • pp.344-348
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    • 2016
  • We developed a 2-channel fiber-optic temperature sensor (FOTS) using a temperature sensing probe, a fiber-optic coupler, transmitting optical fiber, and an optical time domain reflectometer (OTDR). The temperature sensing probe is divided into a sensing probe and a reference probe for accurate thermometry. A sensing probe is composed of a silicon oil, a FC terminator, a brass pipe, and a singlemode optical fiber and the structure of a reference probe is identical with that of the sensing probe excluding a silicon oil. In this study, we measured the modified optical powers of the light signals reflected from the temperature sensing probe placed inside of the water with a thermal variation from 5 to $70^{\circ}C$. Although the optical power of the reference probe was constant regardless of the temperature change, the optical power of the sensing probe decreased linearly as the temperature increased. As experimental results, the FOTS using a subtraction method showed a small difference (i.e., hysteresis) in its response due to heating and cooling. The reversibility and reproducibility of the FOTS were also evaluated.

A literatual studies on the yupung(油風). (油風의 病因, 病機 및 治療藥物에 關한 文獻的 考察)

  • Kim, Nam-uk;Roh, Sek-seon
    • The Journal of Korean Medicine Ophthalmology and Otolaryngology and Dermatology
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    • v.11 no.1
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    • pp.162-179
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    • 1998
  • In the literatual studies on the yupung(油風), the results were as follows. 1. Yupung(油風) was called 'Quijidu(鬼지頭)', 'Quichedu(鬼剃頭)', 'Ballak(髮落)' etc. It was a localized loss of hair in round or oval ares without any subjective symptom 2. The etiology and pathogenesis of Yupung were disorder of vital energy& blood circulation caused by deficiency of blood and wind-dryness syndrome, energy-stagnation and blood stasis, impairment of the liver & kidney. The treatments of Yupung were invigorating the liver & kidney, clearing away heat-evil and cooling blood, nourishing the liver & kidney, activating blood circulation to dissipate blood stasis etc, 3. In the frequency of prescription, the most numerous prescription is Shineuingyangjindan(神應養眞丹) and the next are Tonggyuhwalhyultang(通竅活血湯) & Chilbomiyumdan(七寶美髥丹), 4. In the frequency of medicine, the most numerous medicine is Radix Angelicae Sinensis(當歸) and the next are Rhizoma Rehmanniae Praeparatae(熟地黃) & Rhizoma Ligusiici Chuanxiong(川芎). 5. In classification of drug action, medicines of clearing away wind-heat evil and invigorating yin used to be very busy. 6. In classification of four characters, the most parts are warm medicine. 7. In classification of five tastes, the most numerous tastes are sweet and bitter tastes. 8. In classification of toxicity, the most is non-toxic medicines. 9. In classification of the channel distribution, the most is the medicine that belongs to liver channel. 10. In acupuncture theraphy, it was used 'GV20(百會)', 'G20(風池)', 'GV16(風府)', 'GV14(大椎)', 'LI4(合谷)' etc. in body acupuncture, was used 'S25(天樞)', 'GV14(大椎)', 'B13(肺兪)', 'LI11(曲池)' etc. in moxibustion.

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Study on flow characteristics in LBE-cooled main coolant pump under positive rotating condition

  • Lu, Yonggang;Wang, Zhengwei;Zhu, Rongsheng;Wang, Xiuli;Long, Yun
    • Nuclear Engineering and Technology
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    • v.54 no.7
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    • pp.2720-2727
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    • 2022
  • The Generation IV Lead-cooled fast reactor (LFR) take the liquid lead or lead-bismuth eutectic alloy (LBE) as the coolant of the primary cooling circuit. Combined with the natural characteristics of lead alloy and the design features of LFR, the system is the simplest and the number of equipment is the least, which reflects the inherent safety characteristics of LFR. The nuclear main coolant pump (MCP) is the only power component and the only rotating component in the primary circuit of the reactor, so the various operating characteristics of the MCP are directly related to the safety of the nuclear reactor. In this paper, various working conditions that may occur in the normal rotation (positive rotating) of the MCP and the corresponding internal flow characteristics are analyzed and studied, including the normal pump condition, the positive-flow braking condition and the negative-flow braking condition. Since the corrosiveness of LBE is proportional to the fluid velocity, the distribution of flow velocity in the pump channel will be the focus of this study. It is found that under the normal pump condition and positive-flow braking conditions, the high velocity region of the impeller domain appears at the inlet and outlet of the blade. At the same radius, the pressure surface is lower than the back surface, and with the increase of flow rate, the flow separation phenomenon is obvious, and the turbulent kinetic energy distribution in impeller and diffuser domain shows obvious near-wall property. Under the negative-flow braking condition, there is obvious flow separation in the impeller channel.