• Title/Summary/Keyword: atomic model

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Thermal Analysis of High Level Radioactive Waste Repository Using a Large Model

  • Park, Jeong-Hwa;Kuh, Jung-Eui;Sangki Kwon;Kang, Chul-Hyung
    • Nuclear Engineering and Technology
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    • v.32 no.3
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    • pp.244-253
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    • 2000
  • A Simple Large Model (SLM), which can be used to make thermal calculation for a deep geological repository with finite number of HLW canisters, was developed. In order to develop the SLM, a Simple Basic Model (SBM), which will be a unit of the SLM, was optimized first. The SBM was optimized to achieve the same maximum buffer temperature as that of the Detailed Basic Model (DBM) representing the real geometric aspects of the repository. In contrast to the models with the assumption of infinite number of canisters which cannot consider boundary effect, the SLM can model the real repository with finite number of canisters and thus consider the boundary effect. Thermal results from the SLM can be used to evaluate the reliability of the models, which do not consider boundary effect. This model can also be used to simulate the thermal layout design and to analyze the thermal safety of a deep geological repository as well as an underground laboratory.

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PREDICTION OF THE TRITIUM CONCENTRATION IN THE SOIL WATER AFTER THE OPERATION OF WOLSONG TRITIUM REMOVAL FACILITY

  • CHOI HEUI-JOO;LEE HANSOO;SUH KYUNG SUK;KANG HEE SUK
    • Nuclear Engineering and Technology
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    • v.37 no.4
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    • pp.385-390
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    • 2005
  • The effect of the Wolsong Tritium Removal Facility on the change of tritium concentration in the soil water was assessed by introducing a dynamic compartment model. For the mathematical modeling, the tritium in the environment was thought to come from two different sources. Three global tritium cycling models were compared with the natural background concentration. The dynamic compartment model was used to model the behavior of the tritium from the nuclear power plants at the Wolsong site. The source term for the dynamic compartment model was calculated with the dry and wet deposition rates. The area around the Wolsong nuclear power plants was represented by the compartments. The mechanisms considered in deriving the transfer coefficients between the compartments were evaporation, runoff, infiltration, hydrodynamic dispersion, and groundwater flow. We predicted what the change of the tritium concentration around the Wolsong nuclear power plants would be after future operation of the tritium removal facility to show the applicability of the model. The results showed that the operation of the tritium removal facility would reduce the tritium concentration in topsoil water quickly.

Dynamic equivalent model of a SMART control rod drive mechanism for a seismic analysis

  • Ahn, Kwanghyun;Lee, Jae-Seon
    • Nuclear Engineering and Technology
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    • v.52 no.8
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    • pp.1834-1846
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    • 2020
  • The SMART (System-integrated Modular Advanced ReacTor) is an integral-type small modular reactor developed by KAERI (Korea Atomic Energy Research Institute). This paper discusses the development of a dynamic equivalent model of the SMART control rod drive mechanism that can be efficiently utilized for complicated analysis during the design of the SMART. A semi-empirical approach is used to develop the equivalent model; that is, the equivalent model is defined analytically and verified empirically. Two types of tests, dynamic characteristics tests and seismic loading tests, are conducted for the development and verification of the dynamic equivalent model, respectively. Acceleration response spectra from the seismic analysis based on the developed equivalent model show good agreement with those from the seismic loading tests.