• 제목/요약/키워드: Nuclear Hydrogen System

검색결과 156건 처리시간 0.023초

Assessment of the core-catcher in the VVER-1000 reactor containment under various severe accidents

  • Farhad Salari;Ataollah Rabiee;Farshad Faghihi
    • Nuclear Engineering and Technology
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    • 제55권1호
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    • pp.144-155
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    • 2023
  • The core catcher is used as a passive safety system in new generation nuclear power plants to create a space in the containment for the placing and cooling of the molten corium under various severe accidents. This research investigates the role of the core catcher in the VVER-1000 reactor containment system in mitigating the effects of core meltdown under various severe accidents within the context of the Ex-vessel Melt Retention (EVMR) strategy. Hence, a comparison study of three severe accidents is conducted, including Station Black-Out (SBO), SBO combined with the Large Break Loss of Coolant Accident (LB-LOCA), and SBO combined with the Small Break Loss of Coolant Accident (SB-LOCA). Numerical comparative simulations are performed for the aforementioned scenario with and without the EX-vessel core-catcher. The results showed that considering the EX-Vessel core catcher reduces the amount of hydrogen by about 18.2 percent in the case of SBO + LB-LOCA, and hydrogen production decreases by 12.4 percent in the case of SBO + SB-LOCA. Furthermore, in the presence of an EX-Vessel core-catcher, the production of gases such as CO and CO2 for the SBO accident is negligible. It was revealed that the greatest decrease in pressure and temperature of the containment is related to the SBO accident.

The Magnetic Filtering Vacuum Arc Film Deposition System and Its Applications

  • Wang, G.F.;Zhang, H.X.;Zhang, H.J.;Zhu, H.
    • 한국진공학회지
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    • 제6권S1호
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    • pp.137-140
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    • 1997
  • A cathodic arc with beam filter is employed for the deposition of metallic and hydrogen-free amorphous carbon films. A solenoid filter is used to prevent macropaticles and nonionized atoms from reaching the substrate. The detail transport characters of the filter are presented in the paper. With an optmum filter arrangement we are able to obtain a filter output of 18.4% of the total number of ions produced by the vacuum arc discharge. The deposited amorphous cabon thin film contains no hydrogen and a high fraction of $sp^3$ is determined by XPS. A dense Ti film deposited on H13 steel improves the corrosion resistance of the H13 steel and significant improvements of corrosion resistance were observed by implanting Ti, C in the film.

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Simulating reactive distillation of HIx (HI-H2O-I2) system in Sulphur-Iodine cycle for hydrogen production

  • Mandal, Subhasis;Jana, Amiya K.
    • Nuclear Engineering and Technology
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    • 제52권2호
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    • pp.279-286
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    • 2020
  • In this article, we develop a reactive distillation (RD) column configuration for the production of hydrogen. This RD column is in the HI decomposition section of the sulphur - iodine (SI) thermochemical cycle, in which HI decomposition and H2 separation take place simultaneously. The section plays a major role in high hydrogen production efficiency (that depends on reaction conversion and separation efficiency) of the SI cycle. In the column simulation, the rigorous thermodynamic phase equilibrium and reaction kinetic model are used. The tuning parameters involved in phase equilibrium model are dependent on interactive components and system temperature. For kinetic model, parameter values are adopted from the Aspen flowsheet simulator. Interestingly, there is no side reaction (e.g., solvation reaction, electrolyte decomposition and polyiodide formation) considered aiming to make the proposed model simple that leads to a challenging prediction. The process parameters are determined on the basis of optimal hydrogen production as reflux ratio = 0.87, total number of stages = 19 and feeding point at 8th stage. With this, the column operates at a reasonably low pressure (i.e., 8 bar) and produces hydrogen in the distillate with a desired composition (H2 = 9.18 mol%, H2O = 88.27 mol% and HI = 2.54 mol%). Finally, the results are compared with other model simulations. It is observed that the proposed scheme leads to consume a reasonably low energy requirement of 327 MJ/kmol of H2.

운동 양자 체(Kinetic Quantum Sieving) 효과를 가진 나노다공성 물질을 활용한 수소동위원소 분리 동향 (Research Trend of Crystalline Porous Materials for Hydrogen Isotope Separation via Kinetic Quantum Sieving)

  • 이슬지;오현철
    • 한국재료학회지
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    • 제31권8호
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    • pp.465-470
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    • 2021
  • Deuterium is a crucial clean energy source required for nuclear fusion and is a future resource needed in various industries and scientific fields. However, it is not easy to enrich deuterium because the proportion of deuterium in the hydrogen mixture is scarce, at approximately 0.016 %. Furthermore, the physical and chemical properties of the hydrogen mixture and deuterium are very similar. Therefore, the efficient separation of deuterium from hydrogen mixtures is often a significant challenge when using modern separation technologies. Recently, to effectively separate deuterium, studies utilizing the 'Kinetic Quantum Sieving Effect (KQS)' of porous materials are increasing. Therefore, in this review, two different strategies have been discussed for improving KQS efficiency for hydrogen isotope separation performance using nanoporous materials. One is the gating effect, which precisely controls the aperture locally by adjusting the temperature and pressure. The second is the breathing phenomenon, utilizing the volume change of the structure from closed system to open system. It has been reported that efficient hydrogen isotope separation is possible using these two methods, and each of these effects is described in detail in this review. In addition, a specific-isotope responsive system (e.g., 2nd breathing effect in MIL-53) has recently been discovered and is described here as well.

Small Nuclear Units에 의한 분산전원으로서의 전망(1) (Small Nuclear Units and Distributed Resource Prospects(1))

  • 이상성
    • 대한전기학회:학술대회논문집
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    • 대한전기학회 2005년도 제36회 하계학술대회 논문집 A
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    • pp.223-225
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    • 2005
  • This paper will be introduce a new paradigm and prospects for energy supply system in near future which produces electric and district heat cogeneration with dispersed power grid with small nuclear power units. Recently, in nuclear field, a lot of effort has been done in nuclear major countries to develop small and medium reactor for enhancement of nuclear peaceful use as like in district heating, electric power generation, seawater desalination or hydrogen generation. This paper presents a new way and prospects for power source in distribution system by using the distributed & remote cogeneration system using small reactor.

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초고온가스로의 동심축 이중관형 고온가스덕트에 대한 구조정산 방법론 제안 (Suggestion of Structural Sizing Methodology on a Coaxial Double-tube Type Hot Gas Duct for the VHTR)

  • 송기남;김용완
    • 대한기계학회:학술대회논문집
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    • 대한기계학회 2008년도 추계학술대회A
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    • pp.717-724
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    • 2008
  • Very High Temperature Gas Cooled Reactor (VHTR) has been selected as a high energy heat source for nuclear hydrogen generation, which can produce hydrogen from water or natural gas. A primary hot gas duct (HGD) as a coaxial double-tube type cross vessel is a key component connecting the reactor pressure vessel and the intermediate heat exchanger for the VHTR. In this study, structural sizing methodology for the primary HGD with a coaxial double-tube of the VHTR that produces heat at temperatures in the order of $950^{\circ}C$ was suggested and a structural pre-sizing of it was carried out as an example.

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중대사고시 수소폭발이 격납건물에 미치는 영향 (Hydrogen explosion effects at a containment building following a severe accident)

  • 류명록;박권하
    • Journal of Advanced Marine Engineering and Technology
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    • 제40권3호
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    • pp.165-173
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    • 2016
  • 2011년 3월 11일 리히터 스케일 9.0의 강진과 10-14m파도로 인해 Fukushima Daiichi(FD) 원자력 단지의 주전력과 보조전력이 끊어져 냉각장치가 작동하지 않았고 노심의 열이 제거되지 못해 폭발이 일어나는 사고가 발생했다. 노심의 열이 제거되지 못하면 핵연료 피복재인 지르칼로이(zircaloy)와 같은 금속이 고온 상태에서 수증기와 산화 반응하여 수소를 발생시킨다. 발생된 수소는 격납건물로 방출되는데 방출된 수소가 연소하는 경우 격납건물의 안정성에 영향을 줄 정도의 큰 충격을 유발할 수 있는 수소폭발로 이어질 수 있다. 본 연구에서는 격납건물 내부의 수소 분포를 분석한 연구 [1]에서 제시한 폭발의 위해도가 높은 영역에 대하여 폭발해석을 수행하였으며 수소 폭발이 격납건물의 건전성에 미치는 영향에 대하여 분석하였다. 격납건물 중앙부를 제외하고 수소폭발이 발생하였고 상부에 전체 수소의 40%이상이 모였을 때와 하부 좌측, 우측의 격벽사이에 수소가 모였을 때 큰 폭발이 발생했으며 격납건물 벽면에 큰 응력을 동반하였다.

A Preliminary Study for the Implementation of General Accident Management Strategies

  • Yang, Soo-Hyung;Kim, Soo-Hyung;Jeong, Young-Hoon;Chang, Soon-Heung
    • 한국원자력학회:학술대회논문집
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    • 한국원자력학회 1997년도 추계학술발표회논문집(1)
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    • pp.695-700
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    • 1997
  • To enhance the safety of nuclear power plants, implementation of accident management has been suggested as one of most important programs. Specially, accident management strategies are suggested as one of key elements considered in development of the accident management program. In this study, generally applicable accident management strategies to domestic nuclear power plants are identified through reviewing several accident management programs for the other countries and considering domestic conditions. Identified strategies are as follows; 1) Injection into the Reactor Coolant System, 2) Depressurize the Reactor Coolant System, 3) Depressurize the Steam Generator, 4) Injection into the Steam Generator, 5) Injection into the Containment, 6) Spray into the Containment, 7) Control Hydrogen in the Containment. In addition, the systems and instrumentation necessary for the implementation of .each strategy are also investigated.

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