• 제목/요약/키워드: Nuclear Reaction

검색결과 1,028건 처리시간 0.044초

INTERPARTICLE POTENTIAL OF 10 NANOMETER TITANIUM NANOPARTICLES IN LIQUID SODIUM: THEORETICAL APPROACH

  • KIM, SOO JAE;PARK, GUNYEOP;PARK, HYUN SUN;KIM, MOO HWAN;BAEK, JEHYUN
    • Nuclear Engineering and Technology
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    • 제47권6호
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    • pp.662-668
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    • 2015
  • A suspension of titanium nanoparticles (Ti NPs) in liquid sodium (Na) has been proposed as a method to mitigate the violent sodium-water reaction (SWR). The interparticle potential between Ti NPs in liquid Na may play a significant role in the agglomeration of NPs on the reaction surface and in the bulk liquid Na, since the potential contributes to a reduction in the long-term dispersion stability. For the effective control of the SWR with NPs, a physical understanding of the molecular dynamics of NPs in liquid Na is key. Therefore in this study, the nonretarded Van der Waals model and the solvation potential model are employed to analyze the interparticle potential. The ab initio calculation reveals that a strong repulsive force driven by the solvation potential exceeds the interparticle attraction and predicts the agglomeration energy required for two 10-nm Ti NPs to be $4{\times}10^{-17}J$. The collision theory suggests that Ti NPs can be effective suppressors of the SWR due to the high energy barrier that prevents significant agglomeration of Ti NPs in quiescent liquid Na.

Electrochemical Behaviors of Bi3+ Ions on Inert Tungsten or on Liquid Bi Pool in the Molten LiCl-KCl Eutectic

  • Kim, Beom Kyu;Park, Byung Gi
    • 방사성폐기물학회지
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    • 제20권1호
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    • pp.33-41
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    • 2022
  • Liquid Bi pool is a candidate electrode for an electrometallurgical process in the molten LiCl-KCl eutectic to treat the spent nuclear fuels from nuclear power plants. The electrochemical behavior of Bi3+ ions and the electrode reaction on liquid Bi pool were investigated with the cyclic voltammetry in an environment with or without BiCl3 in the molten LiCl-KCl eutectic. Experimental results showed that two redox reactions of Bi3+ on inert W electrode and the shift of cathodic peak potentials of Li+ and Bi3+ on liquid Bi pool electrode in molten LiCl-KCl eutectic. It is confirmed that the redox reaction of lithium with respect to the liquid Bi pool electrode would occur in a wide range of potentials in molten LiCl-KCl eutectic. The obtained data will be used to design the electrometallurgical process for treating actinide and lanthanide from the spent nuclear fuels and to understand the electrochemical reactions of actinide and lanthanide at liquid Bi pool electrode in the molten LiCl-KCl eutectic.

Interaction between UN and CdCl2 in molten LiCl-KCl eutectic. II. Experiment at 1023 K

  • Zhitkov, Alexander;Potapov, Alexei;Karimov, Kirill;Kholkina, Anna;Shishkin, Vladimir;Dedyukhin, Alexander;Zaykov, Yury
    • Nuclear Engineering and Technology
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    • 제54권2호
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    • pp.653-660
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    • 2022
  • The interaction between UN and CdCl2 in the LiCl-KCl molten eutectic was studied at 1023 K. The chlorination was monitored by sampling and recording the redox potential of the medium. At 1023 K the chlorination of UN with cadmium chloride in the molten LiCl-KCl eutectic proceeds completely and results in the formation of uranium chlorides. The melts of the LiCl-KCl-UCl3 or LiCl-KCl-UCl4 compositions can be obtained by the end of experiment depending on the presence of metallic cadmium in the reaction zone. The higher the concentration of the chlorinating agent, the faster the reaction rate. At [CdCl2]/[UN] = 1.65 (10% excess) the reaction proceeds to completion in about 7.5 h. At [CdCl2]/[UN] = 7 the complete chlorination takes 2.5-3 h.

Preliminary importance analyses on model for pH in the presence of organic impurities in the aqueous phase for a severe accident of a nuclear power plant

  • Yoonhee Lee;Yong Jin Cho
    • Nuclear Engineering and Technology
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    • 제56권6호
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    • pp.2079-2091
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    • 2024
  • In this paper, a model is developed for calculating pH in the presence of organic impurities due to dissolution of paint and/or continuous injection of organic impurities in the sump. The model is implemented in the AnCheBi code for the analysis of chemical behaviors of the iodine in the containment when the pH changes during a severe accident. Validation of the model is performed with P10T2 and P11T1 experiments carried out by AECL in Canada under the BIP project. Importance analyses of the pH calculation model in the AnCheBi code are then performed with the aforementioned experimental data via Latin hypercube sampling on the reaction coefficients, sensitivity analyses of AnCheBi, and calculation of the correlation coefficients between the reaction coefficients and figure of merits (the pH and the concentrations of the various iodine species). From the importance analyses, we provide the sensitivity of the pH calculation model to the change of pH and the concentrations of the various iodine species and the reaction coefficients related with the dominant phenomena underlying the change of pH and the concentrations of the species.

Relative Power Density Distribution Calculations of the Kori Unit 1 Pressurized Water Reactor with Full-Scope Explicit Modeling of Monte Carlo Simulation

  • Kim, Jong-Oh;Kim, Jong-Kyung
    • Nuclear Engineering and Technology
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    • 제29권5호
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    • pp.375-384
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    • 1997
  • Relative power density distributions of the Kori Unit 1 pressurized water reactor are calculated by Monte Carlo modeling with the MCNP code. The Kori Unit 1 core is modeled on a three-dimensional representation of the one-eighth of the reactor in-vessel component with reflective boundaries at 0 and 45 degrees. The axial core model is based on half core symmetry and is divided into four axial segments. Fission reaction density in each rod is calculated by following 100 cycles with 5,000 test neutrons in each cycle after starling with a localized neutron source and ten noncontributing settle cycles. Relative assembly power distributions are calculated from fission reaction densities of rods in assembly. After 100 cycle calculations, the system converges to a k value of 1.00039 $\geq$ 0.00084. Relative assembly power distribution is nearly the same with that of the Kori Unit 1 FSAR. Applicability of the full-scope Monte Carlo simulation in the power distribution calculation is examined by the relative root moan square error of 2.159%.

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Direct Substitution Reaction of Phenylethyl Bromides

  • Jeong, Woon-Sou
    • Nuclear Engineering and Technology
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    • 제5권1호
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    • pp.26-29
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    • 1973
  • 25$^{\circ}$및 35$^{\circ}C$의 아세톤 용액에서 부롬화 훼네틸들의 할로겐 교환반응을 연구하였다. 결과로 이 반응은 전형적인 SN2형 반응이고 염소 교환의 경우 1-부롬화 훼네틸의 입체 반해작용으로 활성화 파라메터에 큰 변화를 가져옴을 알았다.

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