• Title/Summary/Keyword: hydrogen vessel

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스테인레스강 Overlay 용접부의 Disbonding에 관한 연구 1

  • 이영호;윤의박
    • Journal of Welding and Joining
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    • v.1 no.2
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    • pp.45-52
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    • 1983
  • Many pressure vessels for the hot H$\sub$2//H$\sub$2/S service are made of 2+1/4Cr-1Mo steel with austenitic stainless steel overlay to combat agressive corrosion due to hydrogen sulfide. Hydrogen dissolves in to materials during operation, and sometimes gives rise to unfore-seeable damages. Appropriate precautions must, therefore, be taken to avoid the hydrogen induced damages in the design, fabrication and operation stage of such reactor vessels. Recently, hydrogeninduced cracking (or Disbonding) was found at the interface between base metal and stainless weld overlay of a desulfurizing reactor. Since the stainless steel overlay weld metal is subjected to thermal and internal-pressure loads in reactor operation, it is desirable for the overlay weld metal to have high strength and ductility from the stand point of structural safety. In section III of ASME Boiler and Pressure Vessel Code, Post-Weld Heat Treatment(PWHT) of more than one hour per inch at over 1100.deg. F(593.deg. C) is required for the weld joints of low alloy pressure vessel steels. This heat treatment to relieve stresses in the welded joint during construction of the pressure vessel is considered to cause sensitization of the overlay weld metal. The present study was carried out to make clear the diffusion of carbon migration by PWHT in dissimilar metal welded joint. The main conclusion reached from this study are as follows: 1) The theoretical analysis for diffusion of carbon in stainless steel overlay weld metal does not agree with Fick's 2nd law but the general law of molecular diffusion phenomenon by thermodynamic chemical potential. 2) In the stainless steel overlay welded joint, the PWHT at 720.deg. C for 10 hours causes a diffusion of carbon atoms from ferritic steel into austenitic steel according to the theoretical analysis for carbon migration and its experiment. 3) In case of PWHT at 720.deg. C for 10 hours, the micro-hardness of stainless steel weld metal in bonded zone increase very highly in the carburized layer with remarkable hardening than that of weld metal.

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Storage and Delivery of Hydrogen Isotopes (삼중수소 저장기술)

  • Chung, Hong-Suk;Chung, Dong-You;Koo, Dae-Seo;Lee, Ji-Sung;Shim, Myung-Hwa;Cho, Seung-Yon;Jung, Ki-Jung;Yun, Sei-Hun
    • Transactions of the Korean hydrogen and new energy society
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    • v.22 no.3
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    • pp.372-379
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    • 2011
  • A nuclear fusion fuel cycle plant is composed of various subsystems such as a hydrogen isotope storage and delivery system, a tokamak exhaust processing system, and a hydrogen isotope separation system. Korea shares in the construction of its ITER fuel cycle plant with the EU, Japan, and the US, and is responsible for the development and supply of the storage and delivery system. The authors thus present details on the development status of hydrogen isotope storage technologies for nuclear fusion fuel cycle plants. We have developed various hydride beds of different size. We have realized a hydrogen delivery rate of 12.5 $Pam^3/s$ with a typical 1242g-ZrCo bed.

Study on Hydrogen Effect in TIG Welded Stainless Steel (TIG 용접된 스테인리스강의 수소영향에 대한 연구)

  • Lee, Jin-Kyung;Lee, Sang-Pill;Bae, Dong-Su;Lee, Joon-Hyun
    • Journal of Power System Engineering
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    • v.20 no.6
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    • pp.58-63
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    • 2016
  • A stainless steel has high corrosion resistance because of nickel in material, so it is used as materials for transportation and storage of hydrogen. In this study, TIG(tungsten ingot gas) welding was carried out on the stainless steel using the storage vessel of hydrogen. The microscopic structures at each region of TIG welded material such as HAZ, weld and base metals using optical microscope were observed. And the damage behavior of stainless steel that underwent the hydrogen charging using nondestructive evaluation was also studied. Ultrasonic test, which is the most generalized nondestructive technique, was applied to evaluate the relationship between the ultrasonic wave and mechanical properties at each zone of TIG welded stainless steel. The velocity and attenuation coefficients of ultrasonic wave didn't show a remarkable difference at each region of welded stainless steel. However, the attenuation coefficient was the highest at the weld zone when hydrogen charged stainless steel. In addition, acoustic emission test was also used to study the dynamic behavior of stainless steel experienced both hydrogen charging and weld. Lots of AE event at elastic region of stress-strain curve were occurred both the hydrogen charged specimen and the free specimen.

Dehydriding Performance in a Depleted Uranium Bed (감손 우라늄 베드 수소 탈장 성능)

  • KOO, DAESEO;KIM, YEANJIN;YUN, SEI-HUN;CHUNG, HONGSUK
    • Transactions of the Korean hydrogen and new energy society
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    • v.27 no.1
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    • pp.22-28
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    • 2016
  • It is necessary to store and supply hydrogen isotopes for Tokamak operation. A storage and delivery system (SDS) is used for storing hydrogen isotopes as a metal hydride form. We designed and fabricated a depleted uranium (DU) bed to store hydrogen isotopes. The rapid storage of hydrogen isotopes is very important not only for safety reasons but also for the economic design and operation of the SDS. The delivery rate at the desorption temperatures without the operation of a dry pump was analyzed in comparison with that with the operation of the dry pump. The effect of the initial desorption temperatures on the dehydriding of the DU without the operation of the dry pump was measured. The effect of the initial desorption temperatures on the dehydriding of DU with the operation of the dry pump was also measured and analyzed. The primary pressure on the desorption temperatures without the operation of the dry pump was analyzed in comparison with that with the operation of the dry pump. The temperature gradient of the coil heater and the primary vessel was also analyzed. Our results will be used to develop pilot scale hydrogen isotope processes. It was confirmed that dehydriding of a medium-scale DU bed has enabled without the operation of the dry pump.

The effects of activated cooler power on the transient pressure decay and helium mixing in the PANDA facility

  • Kapulla, R.;Paranjape, S.;Fehlmann, M.;Suter, S.;Doll, U.;Paladino, D.
    • Nuclear Engineering and Technology
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    • v.54 no.6
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    • pp.2311-2320
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    • 2022
  • The main outcomes of the experiments H2P6 performed in the thermal-hydraulics large-scale PANDA facility at PSI in the frame of the OECD/NEA HYMERES-2 project are presented in this article. The experiments of the H2P6 series consists of two PANDA tests characterized by the activation of three (H2P6_1) or one (H2P6_2) cooler(s) in an initially stratified and pressurized containment atmosphere. The initial stratification is defined by a helium-rich region located in the upper part of the vessel and a steam/air atmosphere in the lower part. The activation of the cooler(s) results i) in the condensation of the steam in the vicinity of the cooler(s), ii) the corresponding activation of large scale natural circulation currents in the vessel atmosphere, with the result of iii) the re-distribution and mixing of the Helium stratification initially located in the upper half of the vessel and iv) the continuous pressure decay. The initial helium layer represents hydrogen generated in a postulated severe accident. The main question to be answered by the experiments is whether or not the interaction of the different, localized cooler units would be important for the application of numerical methods. The paper describes the initial and boundary conditions and the experimental results of the H2P6 series with the suggestion of simple scaling laws for both experiments in terms of i) the temperature difference(s) across the cooler(s), ii) the transient steam and helium content and iii) the pressure decay in the vessel. The outcomes of this scaling indicate that the interaction between separate, closely localized units does not play a prominent role for the present experiments. It is therefore reasonable to model several units as one large component with equivalent heat transfer area and total water flow rate.

An Experimental Study on the Turbulent Combustion Characteristics of Hydrocarbon Mixtures by Hydrogen Addition (수소를 첨가한 탄화수소 혼합기의 난류연소 특성에 관한 실험적 연구)

  • 김준효;한원희;키도히로유끼
    • Transactions of the Korean Society of Automotive Engineers
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    • v.11 no.6
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    • pp.65-72
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    • 2003
  • In order to clarify turbulent combustion characteristics of hydrocarbon mixtures by hydrogen addition, turbulent burning velocities in a constant volume vessel were measured for both lean and rich hydrocarbon mixtures. Moreover, the configuration characteristics of turbulent flame was investigated in the wrinkled laminar flame region. A laser tomography technique was used to obtain the images of turbulent flame, and quantitative analyses were performed. As a result, the characteristics of turbulent burning velocity was shown a distinct difference with the addition rate of hydrogen between lean and rich mixtures. On the other hand, the obtained tomograms showed that the surface area of turbulent flame depends almost only on the turbulence intensity.

An Experimental Study on Internal Temperature Changes of Type Ⅳ Cylinder according to Filling with Compressed Hydrogen Gas (압축수소가스 충전에 따른 타입 IV 용기의 온도 변화에 관한 실험적 연구)

  • Lee, Seung-Hoon;Kim, Youn-Gyu;Yoon, Kee-Bong
    • 한국신재생에너지학회:학술대회논문집
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    • 2009.06a
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    • pp.644-647
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    • 2009
  • In this paper, the study is researched for related safety standards having experiments concerning temperature changes in type IV cylinder of the Hydrogen fuel cell vehicle. Experiments were performed to acquire temperature data of type IV cylinder according to filling time. The experimental results are shown that internal temperatures of type Ⅳ vessel are over $85^{\circ}C$ at all measured points after 5 minutes at filling 35 MPa and the highest temperature is getting lower when the residual gases are more remained. Consequently, the safety standards need properly limited value through further study for filling flow rate and filling time.

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Development of analysis program for direct containment heating

  • Jiang, Herui;Shen, Geyu;Meng, Zhaoming;Li, Wenzhe;Yan, Ruihao
    • Nuclear Engineering and Technology
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    • v.54 no.8
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    • pp.3130-3139
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    • 2022
  • Direct containment heating (DCH) is one of the potential factors leading to early containment failure. DCH is closely related to safety analysis and containment performance evaluation of nuclear power plants. In this study, a DCH prediction program was developed to analyze the DCH loads of containment vessel. The phenomenological model of debris dispersal, metal oxidation reaction, debris-atmospheric heat transfer and hydrogen jet burn was established. Code assessment was performed by comparing with several separate effect tests and integral effect tests. The comparison between the predicted results and experimental data shows that the program can predict the key parameters such as peak pressure, temperature, and hydrogen production in containment well, and for most comparisons the relative errors can be maintained within 20%. Among them, the prediction uncertainty of hydrogen production is slightly larger. The analysis shows that the main sources of the error are the difference of time scale and the oxidation of cavity debris.

Investigation of a Hydrogen Mitigation System During Large Break Loss-Of-Coolant Accident for a Two-Loop Pressurized Water Reactor

  • Dehjourian, Mehdi;Sayareh, Reza;Rahgoshay, Mohammad;Jahanfarnia, Gholamreza;Shirani, Amir Saied
    • Nuclear Engineering and Technology
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    • v.48 no.5
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    • pp.1174-1183
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    • 2016
  • Hydrogen release during severe accidents poses a serious threat to containment integrity. Mitigating procedures are necessary to prevent global or local explosions, especially in large steel shell containments. The management of hydrogen safety and prevention of over-pressurization could be implemented through a hydrogen reduction system and spray system. During the course of the hypothetical large break loss-of-coolant accident in a nuclear power plant, hydrogen is generated by a reaction between steam and the fuel-cladding inside the reactor pressure vessel and also core concrete interaction after ejection of melt into the cavity. The MELCOR 1.8.6 was used to assess core degradation and containment behavior during the large break loss-of-coolant accident without the actuation of the safety injection system except for accumulators in Beznau nuclear power plant. Also, hydrogen distribution in containment and performance of hydrogen reduction system were investigated.

Application of Nondestructive Technique on Hydrogen Charging Times of Stainless Steel 304L (스테인리스 304L강의 수소장입시간에 대한 비파괴기법 적용)

  • Lee, Jin-Kyung;Hwang, Seung-Kuk;Lee, Sang-Pill;Bae, Dong-Su;Son, Young-Seok
    • Journal of Power System Engineering
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    • v.19 no.5
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    • pp.60-66
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    • 2015
  • Embrittlement of material by hydrogen charging should be cleared for safety of storage vessel of hydrogen and components deal with hydrogen. A stainless steel is generally used as materials for hydrogen transportation and storage, and it has a big advantage of corrosion resistance due to nickel component in material. In this study, microscopic damage behavior of stainless steel according to the hydrogen charging time using nondestructive evaluation was studied. The surface of stainless steel became more brittle as the hydrogen charging time increased. The parameters of nondestructive evaluation were also changed with the embrittlement of stainless steel surface by hydrogen charging. Ultrasonic test, which is the most generalized nondestructive technique, was applied to evaluate the relationship between the ultrasonic wave and mechanical properties of stainless steel by hydrogen charging. The attenuation coefficient of ultrasonic wave was increased with hydrogen charging time because of surface embrittlement of stainless steel. In addition, acoustic emission test was also used to study the dynamic behavior of stainless steel experienced hydrogen charging. AE event at the hydrogen charged specimen was obviously decreased at the plastic zone of stress-strain curves, while the number of event for the specimen of hydrogen free was dramatically generated when compared with the specimens underwent hydrogen charging.