• 제목/요약/키워드: Nuclear Engineering

검색결과 9,563건 처리시간 0.034초

An optimization design study of producing transuranic nuclides in high flux reactor

  • Wei Xu;Jian Li;Jing Zhao;Ding She;Zhihong Liu;Heng Xie;Lei Shi
    • Nuclear Engineering and Technology
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    • 제55권8호
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    • pp.2723-2733
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    • 2023
  • Transuranic nuclides (such as 238Pu, 252Cf, 249Bk, etc.) have a wide range of application in industry, medicine, agriculture, and other fields. However, due to the complex conversion chain and remarkable fission losses in the process of transuranic nuclides production, the generation amounts are extremely low. High flux reactor with high neutron flux and flexible irradiation channels, is regarded as the promising candidate for producing transuranic nuclides. It is of great significance to increase the conversion ratio of transuranic nuclides, resulting in higher efficiency and better economy. In this paper, we perform an optimization design evaluation of producing transuranic nuclides in high flux reactor, which includes optimization design of irradiation target and influence study of reactor core loading. It is demonstrated that the production rate increases with appropriately determined target material and target structure. The target loading scheme in the irradiation channel also has a significant influence on the production of transuranic nuclides.

Design of muon production target system for the RAON μSR facility in Korea

  • Jeong, Jae Young;Kim, Jae Chang;Kim, Yonghyun;Pak, Kihong;Kim, Kyungmin;Park, Junesic;Son, Jaebum;Kim, Yong Kyun;Lee, Wonjun;Lee, Ju Hahn
    • Nuclear Engineering and Technology
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    • 제53권9호
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    • pp.2909-2917
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    • 2021
  • Following the launch of Rare Isotope Science Project in December 2011, a heavy ion accelerator complex in South Korea, named RAON, has since been designed. It includes a muon facility for muon spin rotation, relaxation, and resonance. The facility will be provided with 600 MeV and 100 kW (one-fourth of the maximum power) proton beam. In this study, the graphite target in RAON was designed to have a rotating disk shape and was cooled by radiative heat transfer. This cool-down process has the following advantages: a low-temperature gradient in the target and the absence of a liquid coolant cooling system. Monte Carlo simulations and ANSYS calculations were performed to optimize the target system in a thermally stable condition when the 100 kW proton beam collided with the target. A comparison between the simulation and experimental data was also included in the design process to obtain reliable results. The final design of the target system will be completed within 2020, and its manufacturing is in progress. The manufactured target system will be installed at the RAON in the Sindong area near Daejeon-city in 2021 to carry out verification experiments.

Performance of 3D printed plastic scintillators for gamma-ray detection

  • Kim, Dong-geon;Lee, Sangmin;Park, Junesic;Son, Jaebum;Kim, Tae Hoon;Kim, Yong Hyun;Pak, Kihong;Kim, Yong Kyun
    • Nuclear Engineering and Technology
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    • 제52권12호
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    • pp.2910-2917
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    • 2020
  • Digital light processing three-dimensional (3D) printing technique is a powerful tool to rapidly manufacture plastic scintillators of almost any shape or geometric features. In our previous study, the main properties of light output and transmission were analyzed. However, a more detailed study of the other properties is required to develop 3D printed plastic scintillators with expectable and reproducible properties. The 3D printed plastic scintillator displayed an average decay time constants of 15.6 ns, intrinsic energy resolution of 13.2%, and intrinsic detection efficiency of 6.81% for 477 keV Compton electrons from the 137Cs γ-ray source. The 3D printed plastic scintillator showed a similar decay time and intrinsic detection efficiency as that of a commercial plastic scintillator BC408. Furthermore, the presented estimates for the properties showed good agreement with the analyzed data.

Towards a physics-based description of intra-granular helium behaviour in oxide fuel for application in fuel performance codes

  • Cognini, L.;Cechet, A.;Barani, T.;Pizzocri, D.;Van Uffelen, P.;Luzzi, L.
    • Nuclear Engineering and Technology
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    • 제53권2호
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    • pp.562-571
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    • 2021
  • In this work, we propose a new mechanistic model for the treatment of helium behaviour which includes the description of helium solubility in oxide fuel. The proposed model has been implemented in SCIANTIX and validated against annealing helium release experiments performed on small doped fuel samples. The overall agreement of the new model with the experimental data is satisfactory, and given the mechanistic formulation of the proposed model, it can be continuously and easily improved by directly including additional phenomena as related experimental data become available.