• Title/Summary/Keyword: Upper-reactor temperature

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Evaluation of Microstructure and Mechanical Properties on Post-Weld Heat Treatment in the Heat Affected Zone of SA508 Gr.4N Ni-Mo-Cr Low Alloy Steel for Reactor Pressure Vessel (원자로압력용기용 SA508 Gr.4N Ni-Mo-Cr계 저합금강 용접열영향부의 용접후열처리에 따른 미세조직과 기계적 특성 평가)

  • Lee, Yoon-Sun;Kim, Min-Chul;Lee, Bong-Sang;Lee, Chang-Hee
    • Korean Journal of Metals and Materials
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    • v.47 no.3
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    • pp.139-146
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    • 2009
  • The heat-affected zone (HAZ) of SA508 Gr.4N Ni-Mo-Cr low alloy steel, which has higher Ni and Cr contents than SA508 Gr.3 Mn-Mo-Ni low alloy steel, was investigated on the microstructure and mechanical properties. The HAZ was categorized into seven characteristic zones (CGCG, FGCG, ICCG, SCCG, FGFG, ICIC and SCSC-HAZ) according to the peak temperature from the thermal cycle experienced during multi-pass welding. Post Weld Heat Treatment (PWHT) was conducted in the temperature range of $550{\sim}610^{\circ}C$ for 30 hours to evaluate the effect of PWHT conditions on the microstructure and mechanical properties. Before PWHT, CGHAZ and FGFGHAZ showed high yield strength (YS) ranging from 1000 to 1250 MPa, while YS of SCSCHAZ decreased from 607 MPa (observed for base metal) to 501 MPa. The Charpy impact energies of sub-HAZs fell below 100J at $-29^{\circ}C$, except in the SCSCHAZ. By applying PWHT to sub-HAZ specimens, YS decreased as the PWHT temperature increased. In the case of CGHAZs and FGFGHAZ heat-treated at $610^{\circ}C$, YS dropped drastically to the range of 654~686 MPa. From the Charpy impact test, the upper-shelf energy (USE) increased to approximately 250J and Index temperature ($T_{68J}$) decreased below $-50^{\circ}C$. Specifically, in FGFG, ICIC and SCSC-HAZ, $T_{68J}$ was below -110, which was lower than the case of base metal.

Comparison of Solid Circulation Characteristics with Change of Lower Loop Seal Geometry in a Circulating Fluidized Bed (순환유동층에서 하부 루프실 형태 변화에 따른 고체순환 특성 비교)

  • Lee, Dong-Ho;Jo, Sung-Ho;Jin, Gyoung-Tae;Yi, Chang-Keun;Ryu, Ho-Jung;Park, Seung Bin
    • Korean Chemical Engineering Research
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    • v.52 no.4
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    • pp.522-529
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    • 2014
  • Circulating fluidized bed system consists of SEWGS reactor - lower loop seal - regeneration reactor - riser - cyclone - upper loop seal has been used for solid circulation between the SEWGS reactor and the regeneration reactor in a SEWGS system for pre-combustion $CO_2$ capture. A vertical type lower loop seal has been used in current system but this lower loop seal requires high gas flow rate through the lower loop seal for fluidization and smooth solid circulation, and consequently, causes slugging behavior sometimes. To overcome these disadvantages, inclined type lower loop seal was proposed by this study. Solid circulation characteristics with change of lower loop seal geometry were measured and compared in a bubbling - bubbling - riser type circulating fluidized bed using $CO_2$ absorbent (P-78) as bed material at ambient temperature and pressure. We could conclude that the inclined lower loop seal is better than the vertical type lower loop seal from the viewpoints of minimum flow rate requirement for stable solid circulation and solid height change during solid circulation.

Detection of Thermal Ratcheting Deformation for Cylindrical Shells by Ultrasonic Guided Wave (유도초음파를 이용한 원통형 쉘의 열 라체팅 변형 탐지)

  • Joo, Young-Sang;Lee, Hyeong-Yeon;Kim, Jong-Bum;Park, Chang-Gyu;Lee, Jae-Han
    • Journal of the Korean Society for Nondestructive Testing
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    • v.26 no.5
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    • pp.297-305
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    • 2006
  • The thermal ratcheting deformation at the reactor baffle and upper internal structure of the liquid metal reactor (LMR) can occur due to movement of the hot sodium free surface. In in-service inspection of reactor internals of LMR, a new inspection technique should be developed for the detection of the thermal ratcheting damage. In this study, an inspection technique using ultrasonic guided wave is proposed for the detection of the thermal ratcheting damage of cylindrical vessels. A 316L stainless steel cylindrical shell specimen has been prepared. The thermal ratchet structural tests were cyclically performed by heat-up up to $550^{\circ}C$ with steep temperature gradients along the axial direction after cool-down by cooling water. Ultrasonic guided wave propagation has been characterized by analysis of dispersion curve of the stainless steel plate. The zero-order antisymmetric $A_0$ guided wave has been selected as the optimal mode for detection of the ratcheting deformation. It is confirmed that the thermal ratcheting deformation can be detected by the measurement of transit time difference of circumferentially propagated $A_0$ guided waves.

Preparation of ultrafine aluminum oxide powders by using R.F. induced plasma (고주파 유도 플라즈마를 이용한 산화 알루미늄 초미세분말 제조)

  • Masahiro Kagawa
    • Journal of the Korean Crystal Growth and Crystal Technology
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    • v.5 no.3
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    • pp.269-277
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    • 1995
  • Ultrafine TEX>$Al_2O_3$ powders were prepared from $AlCl_3$ and $Al_2(SO_4)_3$3 by using inductively coupled plasma (lCP) of ultrahigh temperature (above 5000 K) in heat source. The prepared $Al_2O_3$ powders had ${\alpha} - group ({\alpha}, {wdelta} ;and; {\theta})$ phase, a narrow size distribution and around 20 nm in meansize. It could be suggested that gas - solid reaction growth and interparticle sintering occured at the center of ICP tail flame (X = 500 mm) through the results of deposited aggregates - flock, whisker and platy on MgO polycrystal plate. And the formation mechanism of $Al_2O_3$ powders In spray - ICP reactor were described from upper results.

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Thermal-Hydraulic Research Review and Cooperation Outcome for Light Water Reactor Fuel (경수로핵연료 열수력 연구개발 분석 및 연산학 협력 성과)

  • In, Wang Kee;Shin, Chang Hwan;Lee, Chi Young;Lee, Chan;Chun, Tae Hyun;Oh, Dong Seok
    • Transactions of the Korean Society of Mechanical Engineers B
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    • v.40 no.12
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    • pp.815-824
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    • 2016
  • The fuel assembly for pressurized water reactor (PWR) consists of fuel rod bundle, spacer grid and bottom/top end fittings. The cooling water in high pressure and temperature is introduced in lower plenum of reactor core and directed to upper plenum through the subchannel which is formed between the fuel rods. The main thermal-hydraulic performance parameters for the PWR fuel are pressure drop and critical heat flux in normal operating condition, and quenching time in accident condition. The Korea Atomic Energy Research Institute (KAERI) has been developing an advanced PWR fuel, dual-cooled annular fuel and accident tolerant fuel for the enhancement of fuel performance and the localization. For the key thermal-hydraulic technology development of PWR fuel, the KAERI LWR fuel team has conducted the experiments for pressure drop, turbulent flow mixing and heat transfer, critical heat flux(CHF) and quenching. The computational fluid dynamics (CFD) analysis was also performed to predict flow and heat transfer in fuel assembly including the spent fuel assembly in dry cask for interim repository. In addition, the research cooperation with university and nuclear fuel company was also carried out to develop a basic thermal-hydraulic technology and the commercialization.

Numerical Study for Flow Uniformity in Selective Catalytic Reduction(SCR) Process (SCR 공정에서 반응기 내부의 유동 균일화를 위한 수치적 연구)

  • Jung, Yu-Jin;Hong, Sung-Gil;Kim, Min-Choul;Lee, Jae-Jeong;Lee, Gang-Woo;Shon, Byung-Hyun
    • Journal of the Korea Academia-Industrial cooperation Society
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    • v.12 no.10
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    • pp.4666-4672
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    • 2011
  • Performance of NOx removal in SCR(Selective Catalytic Reduction) process depends on such various factors as catalyst factors (catalyst composition, catalyst form, space velocity, etc.), temperature of exhaust gas, and velocity distribution of exhaust gas. Especially the flow uniformity of gas stream flowing into the catalyst layer is believed to be the most important factor to influence the performance. In this research, the flow characteristics of a SCR process at design stage was simulated, using 3-dimensional numerical analysis method, to confirm the uniformity of the gas stream. In addition, the effects of guide vanes, baffles, and perforated plates on the flow uniformity for the inside and catalyst layer of the reactor were studied in order to optimize the flow uniformity inside the SCR reactor. It was found that the installation of a guide vane at the inlet duct L-tube part and the installation of a baffle at the upper part is very effective in avoiding chaneling inside the reactor. It was also found that additional installation of a perforated plate at the lower part of the potential catalyst layer buffers once more the flow for very uniform distribution of the gas stream.

FISSION PRODUCT AND ACTINIDE RELEASE FROM THE DEBRIS BED TEST PHEBUS FPT4: SYNTHESIS OF THE POST TEST ANALYSES AND OF THE REVAPORISATION TESTING OF THE PLENUM SAMPLES

  • Bottomley P.D.W.;Gregoire A.C.;Carbol P.;Glatz J.P.;Knoche D.;Papaioannou D.;Solatie D.;Van Winckel S.;Gregoire G.;Jacquemain D.
    • Nuclear Engineering and Technology
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    • v.38 no.2
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    • pp.163-174
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    • 2006
  • The $Ph{\acute{e}}bus$ FP project is an international reactor safety project. Its main objective is to study the release, transport and retention of fission products in a severe accident of a light water reactor (LWR). The FPT4 test was performed with a fuel debris bed geometry, to look at late phase core degradation and the releases of low volatile fission products and actinides. Post Test Analyses results indicate that releases of noble gases (Xe, Kr) and high-volatile fission products (Cs, I) were nearly complete and comparable to those obtained during $Ph{\acute{e}}bus$ tests performed with a fuel bundle geometry (FPT1, FPT2). Volatile fission products such as Mo, Te, Rb, Sb were released significantly as in previous tests. Ba integral release was greater than that observed during FPT1. Release of Ru was comparable to that observed during FPT1 and FPT2. As in other $Ph{\acute{e}}bus$ tests, the Ru distribution suggests Ru volatilization followed by fast redeposition in the fuelled section. The similar release fraction for all lanthanides and fuel elements suggests the released fuel particles deposited onto the plenum surfaces. A blockage by molten material induced a steam by-pass which may explain some of the low releases. The revaporisation testing under different atmospheres (pure steam, $H_2/N_2$ and steam /$H_2$) and up to $1000^{\circ}C$ was performed on samples from the first upper plenum. These showed high releases of Cs for all the atmospheres tested. However, different kinetics of revaporisation were observed depending on the gas composition and temperature. Besides Cs, significant revaporisations of other elements were observed: e.g. Ag under reducing conditions, Cd and Sn in steam-containing atmospheres. Revaporisation of small amounts of fuel was also observed in pure steam atmosphere.

Assessment of the Habitability for a Cabinet Fire in the Main Control Room of Nuclear Power Plant using Sensitivity Analysis (민감도 분석을 이용한 원전 주제어실의 케비닛 화재에 대한 거주성 평가)

  • Han, Ho-Sik;Lee, Jae-Ou;Hwang, Cheol-Hong;Kim, Joosung;Lee, Sangkyu
    • Fire Science and Engineering
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    • v.31 no.2
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    • pp.52-60
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    • 2017
  • Numerical simulations were performed to evaluate the habitability of an operator for a cabinet fire in the main control room of a nuclear power plant presented in NUREG-1934. To this end, a Fire Dynamics Simulator (FDS), as a representative fire model, was used. As the criteria for determining the habitability of operator, toxic products, such as CO, were also considered, as well as radiative heat flux, upper layer temperature, smoke layer height, and optical density of smoke. As a result, the probabilities of exceeding the criteria for habitability were evaluated through the sensitivity analysis of the major input parameters and the uncertainty analysis of fire model for various fire scenarios, based on V&V (Verification and Validation). Sensitivity analyses of the maximum heat release rate, CO and soot yields, showed that the habitable time and the limit criterion, which determined the habitability, could be changed. The present methodology will be a realistic alternative to enhancing the reliability for a habitability evaluation in the main control room using uncertain information of cabinet fires.

Pyrolytic Gasification Characteristics of Waste Tires and Waste Synthetic Resins (폐타이어 및 폐합성수지류의 건류가스화 특성)

  • 노남선;김광호;신대현;김동찬
    • Resources Recycling
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    • v.9 no.1
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    • pp.27-35
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    • 2000
  • Characteristics of pyrolytic gasification were examined for the waste tire and 7 types of waste synthetic resin, using a bench scale experimental facility. the product gas temperature of waste tires was $150~300^{\circ}C$ and the temperature profile in the combustion zone of the lower reactor part tended to be clearly distinguished from that in the gasification zone of the upper part. However, in the case of waste synthetic resins, there were no clear distinction and temperature fluctuation was severe, depending on the reaction time. Product gas quantity, which depends on that of supplied (1st) air, was found to be 105~135% of the 1st air amount at the steady state. The concentration of noncombustible components in product gas was 80~90 vol.% and the high heating value of the product gas calculated from gas compositions was 1,500~3,000 kcal/N㎥ for waste tire, and 300~2,900 kcal/N㎥ for waste synthetic resins, respectively. Heating value of product gas and combustible gas concentration were increased in proportion to 1st air amount when 1st air amount is below $0.35N\textrm{m}^3$/min.

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The Comparison between Ziegler-Natta and Zirconocene Catalyst on Reaction Conditions and Physical Properties in Polymer in Propylene Polymerization (프로필렌 중합에 있어서 Ziegler-Natta 촉매와 Zirconocene 촉매의 중합 조건과 중합체의 물성 비교)

  • 이성철;남영곤;정석진
    • Polymer(Korea)
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    • v.24 no.4
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    • pp.437-444
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    • 2000
  • Propylene polymerizations were carried out by using rac-Et(Ind)$_2$ZrCl$_2$ (Zirconocene catalyst) and a commercial third generation Ziegler-Natta catalyst in a semibatch reactor. From the polymerization reactions, the optimum reaction conditions and the physical properties of polymers produced from each catalyst system were investigated. The optimum reaction temperatures of rac-Et(Ind)$_2$ZrCl$_2$ and Ziegler-Natta catalyst were 5$0^{\circ}C$, 4$0^{\circ}C$, respectively. On the basis of the results for the produced polymer particle size distributions and the catalytic activities of polymerization reaction, the reaction temperature should be considered as an important factor for the successful polymerization reactions. Especially, the polymer was conglomerated in the higher reaction temperature. It was found that there was an upper limitation to co-catalyst concentration. Reaction rates and polymer yields rather decreased with increasing the concentration of to-catalyst, i.e., MAO and TEAl affected only polymerization activities, but the PEEB in Ziegler-Natta catalyst system affected isotactic indexes of produced polymer as well as activities. Based on these observations, the production yield seems to exhibit a first order lineal relationship to the partial pressure of monomer.

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