• 제목/요약/키워드: Spallation products

검색결과 4건 처리시간 0.016초

Overview of CSNS tantalum cladded tungsten solid Target-1 and Target-2

  • Wei, Shaohong;Zhang, Ruiqiang;Ji, Quan;Li, Changfeng;Zhou, Bin;Lu, Youlian;Xu, Jun;Zhou, Ke;Zhao, Chongguang;He, Ning;Yin, Wen;Liang, Tianjiao
    • Nuclear Engineering and Technology
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    • 제54권5호
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    • pp.1535-1540
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    • 2022
  • A solid tungsten target was used at the China Spallation Neutron Source (CSNS) with 100 kW proton beam power. To improve the lifetime, hot isostatic pressing (HIP) process was selected to bond tantalum cladding with tungsten plates. Radioactive isotope 182Ta, an activation product of tantalum, was found in the cooling water after a period of operation, however, no radioactive isotopes of 187W was found, which shows the tantalum layer remained mostly intact. The CSNS Target-1 had been operating safely for three years and was replaced by Target-2 in August 2020.

핵파쇄잔류물질의 지표면도달량 측정결과를 이용한 기후와 대기구조의 불안정변화에 미치는 영향 (Further evidence of changing stability of atmosphere and climate on spallation product measurement)

  • Hartwig, Sylvius
    • 한국산업안전학회:학술대회논문집
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    • 한국안전학회 2003년도 춘계 학술논문발표회 논문집
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    • pp.17-20
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    • 2003
  • 대기권내의 적외선반응 기체들의 농도증가에 따라 여러 가지의 기후에 미치는 변수들의 변화뿐만 아니라, 대기권의 역학조건의 변화까지 체험되어지고 있다. 대기권의 역학은 30년으로 정의된 기후변화의 주기보다 훨씬 짧은 주기를 지니고 있다. 이들 변화들은 수십년 이상의 시간동안에 지표면에 도달한 일련의 핵파쇄(spallation) 잔류물질들의 농도측정결과들을 바탕으로 논의되어진다.

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A Preliminary Design Concept of the HYPER System

  • Park, Won S.;Tae Y. Song;Lee, Byoung O.;Park, Chang K.
    • Nuclear Engineering and Technology
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    • 제34권1호
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    • pp.42-59
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    • 2002
  • In order to transmute long-lived radioactive nuclides such as transuranics(TRU), Tc-99, and I- l29 in LWR spent fuel, a preliminary conceptual design study has been performed for the accelerator driven subcritical reactor system, called HYPER(Hybrid Power Extraction Reactor) The core has a hybrid neutron energy spectrum: fast and thermal neutrons for the transmutation of TRU and fission products, respectively. TRU is loaded into the HYPER core as a TRU-Zr metal form because a metal type fuel has very good compatibility with the pyre- chemical process which retains the self-protection of transuranics at all times. On the other hand, Tc-99 and I-129 are loaded as pure technetium metal and sodium iodide, respectively. Pb-Bi is chosen as a primary coolant because Pb-Bi can be a good spallation target and produce a very hard neutron energy spectrum. As a result, the HYPER system does not have any independent spallation target system. 9Cr-2WVTa is used as a window material because an advanced ferritic/martensitic steel is known to have a good performance under a highly corrosive and radiation environment. The support ratios of the HYPER system are about 4∼5 for TRU, Tc-99, and I-129. Therefore, a radiologically clean nuclear power, i.e. zero net production of TRU, Tc-99 and I-129 can be achieved by combining 4 ∼5 LWRs with one HYPER system. In addition, the HYPER system, having good proliferation resistance and high nuclear waste transmutation capability, is believed to provide a breakthrough to the spent fuel problems the nuclear industry is faced with.

Preliminary Corrosion Model in Isothermal Pb and LBE Flow Loops

  • Lee, Sung Ho;Cho, Choon Ho;Song, Tae Yung
    • Corrosion Science and Technology
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    • 제5권6호
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    • pp.201-205
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    • 2006
  • HYPER(Hybrid Power Extraction Reactor) is the accelerator driven subcritical transmutation system developed by KAERI(Korea Atomic Research Institute). HYPER is designed to transmute long-lived transuranic actinides and fission products such as Tc-99 and I-129. Liquid lead-bismuth eutectic (LBE). Has been a primary candidate for coolant and spallation neutron target due to its appropriate thermal-physical and chemical properties, However, it is very corrosive to the common steels used in nuclear installations at high temperature. This corrosion problem is one of the main factors considered to set the upper limits of temperature and velocity of HYPER system. In this study, a parametric study for a corrosion model was performed. And a preliminary corrosion model was also developed to predict the corrosion rate in isothermal Pb and LBE flow loops.