• Title/Summary/Keyword: KHNP

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Long-term Radiation Dose Reduction Plan of KHNP

  • Kim, Saeng-Ki;Shin, Sang-Woon;Lim, Byoung-Chan
    • Journal of Radiation Protection and Research
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    • v.28 no.2
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    • pp.137-143
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    • 2003

  • Annual radiation dose limit to radiation worker was substantially lowered in Korea by the adoption of 1990 recommendations of the International Commission on Radiation Protection (ICRP 60) in its legislation. On the other hand, radiation management environment in nuclear power plants is getting more worse because of the accumulation of radiation sources inside the system and the frequent need for maintenance according as the operation years of nuclear power plants increase. Therefore, Korea Hydro & Nuclear power Co., Ltd. (KHNP) has established a long-term 10 years plan from 2001 to 2010 for the reduction of radiation dose to workers. The plan is aimed for the reduction of annual dose per unit averaged over 5 years from 0.9 man-Sv in 2001 to 0.75 man-Sv in 2010 by radiation source reduction, equipment/tool improvement or new equipment development for easy maintenance, and the improvement of administration and system.

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Allicin reduces expression of Intercellular Adhesion Molecule-1 (ICAM-1) in gamma-irradiated endothelial cells: Involvement of p38 MAP kinase signalling pathway.

  • Son, Eun-Hwa;Mo, Sung-Ji;Cho, Seong-Jun;Yang, Kwang-Hee;Rhee, Dong-Kwon;Pyo, Suhk-Neung
    • Proceedings of the PSK Conference
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    • 2002.10a
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    • pp.307.1-307.1
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    • 2002

  • Inflammation is a frequent radiation-induced following therapeutic irradiation. Since the upregulation of adhesion molecules on endothelial cell surface has been known to be associated with inflammation. interfering with the expression of adhesion molecules is an important therapeutic target. We examined the effect of allicin. a major component of garlic. on the induction of intercellular adhesion molecule-1 (lCAM-1) by gamma-irradiation and the mechanisms of its effect in gamma-irradiated human umbilical vein endothelial cells (HUVECs). (omitted)

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Module level EMC verification method for replacement items in nuclear power plant

  • Hee-Taek Lim;Moon-Gi Min;Hyun-Ki Kim;Gwang-Hyun Lee;Chae-Hyun Yang
    • Nuclear Engineering and Technology
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    • v.55 no.7
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    • pp.2407-2418
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    • 2023

  • Internal replaceable electronic module substitutions can impact EMC (ElectroMagnetic Compatibility) qualification testing and results if EMC testing is conducted at the cabinet level. The impact of component substitutions on EMC qualification results therefore should be evaluated. If a qualitative evaluation is not adequate to ensure that the modified product will not impact the cabinet level EMC qualification results, a new qualification testing should be conducted. Component level retesting should be conducted under electromagnetically equivalent conditions with the cabinet level test. This paper analyzes the propagation of conducted susceptibility test waveforms in a representative cabinet and evaluates the impact of component substitutions on cabinet level EMC qualification results according to the location of the replacement items. A guideline for a qualitative evaluation of the impact of component substitutions is described based on the propagation of the conducted susceptibility test waveforms. A module level test method is also described based on an analysis of the shielding effectiveness of the cabinet.

  • https://doi.org/10.1016/j.net.2023.03.012 인용 PDF

A study on the dose evaluation of critical groups for unrestricted reuse of the site after the decommissioning of Kori Unit 1

  • Hyung-Woo Seo;Gang-Woo Ryu;Young-Il Na;Chan-Geun Park;Jin-Won Son;Cheon-Woo Kim
    • Nuclear Engineering and Technology
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    • v.56 no.8
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    • pp.3359-3368
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    • 2024

  • In the calculation of DCGLs using RESRAD code, the selection of input parameter values is paramount, which is basically possible when specific measures for selecting reuse scenarios and probabilistic evaluation methods are established. When referring to the impact of the age group considered in the environmental impact assessment among the existing operations of the plant, it may also need to be applied in the decommissioning project, and there will be considerations along with site reuse scenarios and probabilistic evaluations. Therefore, the main purpose of this study is to distinguish the types of exposure affected by residual radioactivity contamination during the process of deriving DCGL to be used in the final site release stage of NPPs and to evaluate them by reasonably assigning age group parameter values. In addition, the case of entering a single value for parameter values by age group and the case of entering probabilistic distributions were compared and analyzed.

  • https://doi.org/10.1016/j.net.2024.03.036 인용 PDF