• 제목/요약/키워드: tritium

검색결과 278건 처리시간 0.053초

Synthesis of $^3H$-Labeled dammarane triterpene glycosides of Korean ginseng

  • Han, Byung-Hoon;Woo, Lin-Keun
    • Archives of Pharmacal Research
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    • 제1권1호
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    • pp.27-32
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    • 1978
  • A procedure of $^3H$-radio labeling synthesis for the dammarane triterpene glycosides of Korean ginseng was established by using the ginsenoside $Rg_1$ as starting material. The protons in $C-{11}$ and $C_{13}$ of the aglycone moiety of the glycoside were exchanged with tritium by keto-enol tautomerization of 12-keto-ginsenoside $Rg_1$ which was prepared by partial acetylation, Sarett oxidation and saponification, producing nona-acetate, nonaside $Rg_1$. The acety1-ketone and 12-keto-derivative of ginsenotritated ketone was reduced by metallic sodium and isoproponol to produce the end product $^3H$-ginsenoside $Rg_1$ with 3% radio-chemical recovery in one experiment.

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원자핵 융합 발전소의 삼중수소 유출 사고 예측 (Predicting the Tritium Release Accident in a Nuclear Fusion Plant)

  • 양희중
    • 품질경영학회지
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    • 제26권1호
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    • pp.201-212
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    • 1998
  • A methodology of the safety analysis on the fusion power plant is introduced. It starts with the understanding of the physics and engineering of the plant followed by the assessment of the tritium inventory and flow rate. We a, pp.y the probabilistic risk assessment. An event tree that explains the propagation of the accident is constructed and then it is translated in to an influence diagram, that is accident is constructed and then it is translated in to an influence diagram, that is statistically equivalent so far as the parameter updating is concerned. We follow the Bayesian a, pp.oach where model parameters are treated as random variables. We briefly discuss the parameter updating scheme, and finally develop the methodology to obtain the predictive distribution of time to next severe accident.

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Parametric Analysis of Design Capacity for Tritium Removal Facility

  • 손순환;정양근;이철언
    • 한국원자력학회:학술대회논문집
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    • 한국원자력학회 1997년도 춘계학술발표회논문집(2)
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    • pp.250-255
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    • 1997
  • 중수로형(PHWR) 원자력발전소는 감속재와 냉각재로 중수를 사용하고 있어 방사성 수소동위원소인 삼중수소 생성량이 경수로에 비해 크며 계통내 삼중수소 축적량은 운전년수에 따라 증가하게 된다. 중수로형 원전에서 삼중수소 저감화를 위한 장기 대책으로 Tritium Removal Facility를 적용하는 경우, 우선적으로 괴려하여야 할 사항은 적절한 TRF의 용량을 결정하는 것이다. 이는 초기 시설 투자비뿐만 아니라 설비 및 운전의 신뢰도와 이용율에도 영향을 미치므로 연속운전이 가능하도록 용량을 결정하는 것이 중요하다. 이를 위해 감속재를 대상으로 삼중수소 농도 목표치, 삼중수소 농도 목표치 도달기간, 탈 삼중수소율, TRF 적용시점이 TRF 처리량과 촉매탑 높이에 미치는 영향을 분석하였다. 삼중수소 농도 목표치는 5~15Ci/kg, 도달기간은 3~8년, 탈 삼중수소율은 0.05~0.4, TRF 적용시점은 가동 후 10~20년이 적절한 것으로 확인되었다.

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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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    • 제50권8호
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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.