• 제목/요약/키워드: Tritium storage

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B형 삼중수소 운반용기 안정성 평가 (Safety evaluation of type B transport container for tritium storage vessel)

  • 이민수;백승우;김광락;안도희;임성팔;정홍석;최희주;최종원;손순환;송규민
    • 방사성폐기물학회지
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    • 제5권2호
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    • pp.155-169
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    • 2007
  • 월성 원자력 발전소의 TRF 시설에서 수집된 트리튬을 metal hydride 형태로 보관하고 있는 500 kCi급 트리튬 1차 저장용기를 발전소 밖의 폐기물 저장고로 안전하게 운반하기 위하여 트리튬 운반용기를 개발하였다. B형 운반용기의 기술기준을 적용하여 구조평가, 열평가, 방사선차폐평가, 격납평가 등을 수행하여 운반용기의 안전성을 분석하였다. 트리튬 운반용기는 정상운반조건 및 사고운반조건에서도 격납 경계가 손상되지 않는다고 평가되었다. 붕괴열로 인한 운반용기 내부 저장용기의 온도상승은 수치해석 결과, 원통형 모델에서는 $134.8^{\circ}C$로 나타났다. 운반사고 조건에 대한 열 평가로서 $800^{\circ}C$ 외부환경에 30분간 노출되었을 경우에는 단열재만의 열차폐를 고려하여 계산한 결과, 약 $405^{\circ}C$로 나타났으며, 내부 온도 상승은 1차 격납 경계인 1차 저장용기의 허용 온도인 $550^{\circ}C$에도 미치지 못하였다. 격납 차폐 평가에서도 사고조건인 $800^{\circ}C$의 외부 환경에 노출된 경우에서도 충분히 운반용기의 격납 성능을 유지할 수 있다고 판단되었다. 방사선에 대한 차폐 특성을 조사한 결과, 트리튬에서 발생된 ${\beta}-ray$ 선량은 1차 저장용기 외부 표면에서 0으로 계산되었다. 이상과 같이 500 kCi 급 트리튬 운반용기에 대한 안전성을 평가한 결과, 운반사고조건에서도 트리튬 운반용기는 전혀 이상이 없는 것으로 나타났다.

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삼중수소 저장용기 이종용접부의 수소취화 거동 평가 (I) (Evaluations of Hydrogen Embrittlement Behaviours on Dissimilar Welding Part of SDS Bottles (I))

  • 조경원;최재하;장민혁;이영상;홍태환
    • 한국수소및신에너지학회논문집
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    • 제26권2호
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    • pp.114-119
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    • 2015
  • Nowdays, fossil fuels have been used as an important resource in development of industry. But it is limited and caused climate change such as pollution and global warming. So nuclear fusion research is being issued with tritium to develop eco-friendly and sustainable energy. Republic of Korea is in charge of Storage and Delivery System (SDS) in the International Thermonuclear Experimental Reactor (ITER), weld present in the SDS bottles are easily exposed to the hydrogen embrittlement of special characteristics of the hydrogen in hydrogen atmosphere, When the hydrogen embrittlement is rapidly progresses, the cracking is generated in the weld zone. Due to this cracking, the risk of leakage of tritium into the atmosphere occurs. In this study, hydrogen heat treatment was processed through the Pressure-Composition-Temperature (PCT) device according to the time variation. Also mechanical properties such as rupture strength test, three point bend test and hardness test in accordance with the respective time have been conducted and the fracture was observed by scanning electron microscopy(SEM) after the mechanical properties evaluation.

ZrCo 기반 저장용기로부터 삼중수소 공급을 위한 수소 방출에 대한 수치해석적 연구 (II) (A Numerical Investigation of Hydrogen Desorption Reaction for Tritium Delivery from Tritium Storage Based on ZrCo)

  • 유하늘;조아래;곽건희;윤세훈;장민호;강현구;주현철
    • 한국수소및신에너지학회논문집
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    • 제24권1호
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    • pp.36-43
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    • 2013
  • In this paper, a three-dimensional hydrogen desorption model is applied to a thin double-layered annulus ZrCo hydride bed and validated against the temperature evolution data measured by Kang et al. The present model reasonably captures the bed temperature evolution behavior and the 90% hydrogen discharging time. In addition, the performance of thin double-layered annulus bed is evaluated by comparing with a simple cylindrical bed using hydrogen desorption model. This study provides multi-dimensional contours such as temperature and H/M atomic ratio in the metal hydride region. This numerical study provides fundamental understanding during hydrogen desorption process and indicates that efficient design of the metal hydride bed is critical to achieve rapid hydrogen discharging performance. The present three-dimensional hydrogen desorption model is a useful tool for the optimization of bed design and operating conditions.

What Can Radiation Protection Experts Contribute to the Issue of the Treated Water Stored in the Damaged Fukushima Daiichi Nuclear Power Plant?

  • Yamaguchi, Ichiro
    • Journal of Radiation Protection and Research
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    • 제46권1호
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    • pp.24-31
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    • 2021
  • Decommissioning efforts are underway at the reactor where the accident occurred, namely the damaged Tokyo Electric Power Company (TEPCO) Fukushima Daiichi Nuclear Power Plant (FDNPP). However, a large amount of groundwater flowing into the site has become contaminated with radioactive substances and is stored in tanks on site, which has hampered the decommissioning work. Although the inflow of groundwater has been greatly reduced through measures such as the construction of frost walls, approximately 170 ㎥ of water treated by the Advanced Liquid Processing System (ALPS) is being stored in tanks, each day. The tanks used to store this treated water are expected to become full by around the summer of 2022. It is not easy to get people to understand the efforts of all concerned parties, and providing clear information to these concerned parties is also a challenge. Questions have also been raised regarding whether other alternatives have been fully explored in the ALPS subcommittee. Some people have commented that the answers to the questions raised regarding the biological effects of tritium transmutation are inadequate. Some suspect that the answers are too detailed and incomprehensible, and that the respondents may be manipulating the public with some malicious intent. In any case, each possible plan presents both advantages and disadvantages, depending on the people who are involved. That makes it an ethical and vexing issue that can sway decisions, as perspectives change. While the environmental release plan is scientifically safe, it may represent a painful alternative. On the other hand, a more careful and imaginative approach to the idea of continued storage in tanks or other forms of storage may reveal some troublesome hidden disadvantages. Under these circumstances, experts must be prepared to answer people's questions in a comprehensive and robust manner.

수소동위원소 저장용 ZrCo용기의 급속 냉각 성능 평가 (Rapid Cooling Performance Evaluation of a ZrCo bed for a Hydrogen Isotope Storage)

  • 이정민;박종철;구대서;정동유;윤세훈;백승우;정흥석
    • 한국수소및신에너지학회논문집
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    • 제24권2호
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    • pp.128-135
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    • 2013
  • The nuclear fuel cycle plant is composed of various subsystems such as a fuel storage and delivery system (SDS), a tokamak exhaust processing system, a hydrogen isotope separation system, and a tritium plant analytical system. Korea is sharing in the construction of the International Thermonuclear Experimental Reactor (ITER) fuel cycle plant with the EU, Japan, and the US, and is responsible for the development and supply of the SDS. Hydrogen isotopes are the main fuel for nuclear fusion reactors. Metal hydrides offer a safe and convenient method for hydrogen isotope storage. The storage of hydrogen isotopes is carried out by absorption and desorption in a metal hydride bed. These reactions require heat removal and supply respectively. Accordingly, the rapid storage and delivery of hydrogen isotopes are enabled by a rapid cooling and heating of the metal hydride bed. In this study, we designed and manufactured a vertical-type hydrogen isotope storage bed, which is used to enhance the cooling performance. We present the experimental details of the cooling performances of the bed using various cooling parameters. We also present the modeling results to estimate the heat transport phenomena. We compared the cooling performance of the bed by testing different cooling modes, such as an isolation mode, a natural convection mode, and an outer jacket helium circulation mode. We found that helium circulation mode is the most effective which was confirmed in our model calculations. Thus we can expect a more efficient bed design by employing a forced helium circulation method for new beds.

우라늄 베드 초기온도 및 헬륨농도의 수소 흡장 영향 (Hydriding Performance in a Uranium Bed depending on the Initial Bed Temperatures and Helium Contents)

  • 구대서;김연진;정광진;윤세훈;정흥석
    • 한국수소및신에너지학회논문집
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    • 제27권2호
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    • pp.163-168
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    • 2016
  • Korea has been developing nuclear fusion fuel storage and delivery system (SDS) technologies including a basic scientific study on hydrogen storage. To develop nuclear fusion technology, it is necessary to store and supply hydrogen isotopes needed for Tokamak operation. SDS is used for storing hydrogen isotopes as a metal hydride form. The rapid hydriding of tritium is very important not only for safety reasons but also for the economic design and operation of the SDS. In this study, we designed and fabricated a medium-scale getter bed of depleted uranium (DU). The hydriding of DU has been measured by varying the initial temperature ($100-300^{\circ}C$) of the DU getter bed to investigate the influence of the cooling temperature. Furthermore, we analyzed the effect of a helium blanket on the hydriding performance with 0 - 12% helium content in hydrogen.

삼중수소 저장을 위한 ZrCo 저장재에서의 수소 흡장에 대한 수치해석적 연구 (I) (A Numerical Investigation of Hydrogen Absorption Reaction Based on ZrCo for Tritium Storage (I))

  • 유하늘;윤세훈;장민호;강현구;주현철
    • 한국수소및신에너지학회논문집
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    • 제23권5호
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    • pp.448-454
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    • 2012
  • In this paper, a three-dimensional hydrogen absorption model is applied to a thin double-layered annulus ZrCo hydride bed and validated against the temperature evolution data measured by Kang et al. The present model reasonably captures the bed temperature evolution behavior and the 99% hydrogen charging time. The equilibrium pressure expression for hydrogen absorption on ZrCo is derived as a function of temperature and the H/M atomic ratio based on the pressure-composition isotherm data given by Konishi et al. In addition, this present model provides multi-dimensional contours such as temperature and H/M atomic ratio in the thin doublelayered annulus metal hydride region. This numerical study provides fundamental understanding during hydrogen absorption process and indicates that efficient design of the metal hydride bed is critical to achieve rapid hydrogen charging performance. The present three-dimensional hydrogen absorption model is a useful tool for the optimization of bed design and operating conditions.