• Title/Summary/Keyword: Transmutation

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Youzaijing's Pathologic View on the Outbreak Region of Chest Bind (결흉(結胸)의 발병 부위에 대한 우재경(尤在涇)의 병리관)

  • Chough, Won-Joon
    • Journal of Physiology & Pathology in Korean Medicine
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    • v.22 no.4
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    • pp.733-739
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    • 2008
  • It was said that the epigastric region was the outbreak region of chest bind on Shanghanlon. But successive medical men annotated the epigastric region as the chest, which caused the misunderstanding that chest bind was a chest trouble. However Youzaijing, a medical man in Qing dynasty, presented that the epigastric region meant stomach and the middle of stomach did intestines, comparing Dachengqi-tang with Daxianxiong-tang. This view agreed with Huatuo's six-region-transmutation theory. Taojiean and Zhangjingyue also criticized on the six-meridian-transmutation theory, proposing that the change of cold damage didn't go by the fixed rules. This reflected the oriental medical pathologic view that pathogen invaded and advanced to the weak region by the relations between healthy qi and pathogen, and it criticized on the doctrinarian interpretation of Shanghanlon as Neijing. Huatuo insisted that stomach was the final stage of cold damage by presenting that theory. And this theory became a philological basis on Youzaijing's pathologic view.

Thermal-Hydraulic, Structural Analysis and Design of Liquid Metal Target System (액체금속 표적 시스템의 열적, 구조적 건전성 평가 및 설계)

  • 이용석;정창현
    • Journal of Energy Engineering
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    • v.10 no.3
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    • pp.294-298
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    • 2001
  • A research for transmutation reactor is in progress to transmute high radioactive isotopes into low radioactive ones. In this study, thermal-hydraulic and structural analysis was performed to design liquid metal target system that would be used in subcritical transmutation reactor. Diffuse plate installation was considered to enhance cooling of window. And thermal-structural analysis of window was performed varying window thickness, beam power, and coolant flow rate to determine target system design valuers. It is ensured that maximum window temperature and stress would be acceptable in the design condition.

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Radiation damage to Ni-based alloys in Wolsong CANDU reactor environments

  • Kwon, Junhyun;Jin, Hyung-Ha;Lee, Gyeong-Geun;Park, Dong-Hwan
    • Nuclear Engineering and Technology
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    • v.51 no.3
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    • pp.915-921
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    • 2019
  • Radiation damage due to neutrons has been calculated in Ni-based alloys in Wolsong CANDU reactor environments. Two damage parameters are considered: displacement damage, and transmutation gas production. We used the SPECTER and SRIM computer codes in quantifying radiation damage. In addition, damage caused by Ni two-step reactions was considered. Estimations were made for the annulus spacers in a CANDU reactor that are located axially along a fuel channel and made of Inconel X-750. The calculation results indicate that the transmutation gas production from the Ni two-step reactions is predominant as the effective full power year increases. The displacement damage due to recoil atoms produced from Ni two-step reactions accounts for over 30% out of the total displacement damage.

Monte Carlo analysis of LWR spent fuel transmutation in a fusion-fission hybrid reactor system

  • Sahin, Sumer;Sahin, Haci Mehmet;Tunc, Guven
    • Nuclear Engineering and Technology
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    • v.50 no.8
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    • pp.1339-1348
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    • 2018
  • The aim of this paper is to determine neutronic performances of the light water reactor (LWR) spent fuel mixed with fertile thorium fuel in a FFHR. Time dependent three dimensional calculations for major technical data, such as blanket energy multiplication, tritium breeding ratio, cumulative fissile fuel enrichment and burnup have been performed by using Monte Carlo Neutron-Particle Transport code MCNP5 1.4, coupled with a novel interface code MCNPAS, which is developed by our research group. A self-sustaining tritium breeding ratio (TBR>1.05) has been kept throughout the calculations. The study has shown that the fissile fuel quality will be improved in the course of the transmutation of the LWR spent in the FFHR. The latter has gained the reusable fuel enrichment level conventional LWRs between one and two years. Furthermore, LWR spent fuel - thorium mixture provides higher burn-up values than in light water reactors.