• Title/Summary/Keyword: HANARO Reactor

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Impact of boundary layer simulation on predicting radioactive pollutant dispersion: A case study for HANARO research reactor using the WRF-MMIF-CALPUFF modeling system

  • Lim, Kyo-Sun Sunny;Lim, Jong-Myung;Lee, Jiwoo;Shin, Hyeyum Hailey
    • Nuclear Engineering and Technology
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    • v.53 no.1
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    • pp.244-252
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    • 2021

  • Wind plays an important role in cases of unexpected radioactive pollutant dispersion, deciding distribution and concentration of the leaked substance. The accurate prediction of wind has been challenging in numerical weather prediction models, especially near the surface because of the complex interaction between turbulent flow and topographic effect. In this study, we investigated the characteristics of atmospheric dispersion of radioactive material (i.e. 137Cs) according to the simulated boundary layer around the HANARO research nuclear reactor in Korea using the Weather Research and Forecasting (WRF)-Mesoscale Model Interface (MMIF)-California Puff (CALPUFF) model system. We examined the impacts of orographic drag on wind field, stability calculation methods, and planetary boundary layer parameterizations on the dispersion of radioactive material under a radioactive leaking scenario. We found that inclusion of the orographic drag effect in the WRF model improved the wind prediction most significantly over the complex terrain area, leading the model system to estimate the radioactive concentration near the reactor more conservatively. We also emphasized the importance of the stability calculation method and employing the skillful boundary layer parameterization to ensure more accurate low atmospheric conditions, in order to simulate more feasible spatial distribution of the radioactive dispersion in leaking scenarios.

  • https://doi.org/10.1016/j.net.2020.06.011 인용 PDF KSCI

Estimation of nuclear heating by delayed gamma rays from radioactive structural materials of HANARO

  • Noh, Tae-yang;Park, Byung-Gun;Kim, Myong-Seop
    • Nuclear Engineering and Technology
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    • v.50 no.3
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    • pp.446-452
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    • 2018

  • To improve the accuracy and safety of irradiation tests in High flux Advanced Neutron Application ReactOr (HANARO), the nuclear energy deposition rate, which is called nuclear heating, was estimated for an irradiation capsule with an iridium sample in the irradiation hole in order. The gamma rays emitted from the radioisotopes (RIs) of the structural materials such as flow tubes of fuel assemblies and heavy water reflector tank were considered as radiation source. Using the ORIGEN2.1 code, emission rates of delayed gamma rays were calculated in consideration of the activation procedure for 8 years and 2 months of HANARO operation. Calculated emission rates were used as a source term of delayed gamma rays in the MCNP6 code. By using the MCNP code, the nuclear heating rates of the irradiation capsules in the inner core, outer core, and heavy water reflector tank were estimated. Calculated nuclear heating in the inner core, outer core, and heavy water reflector tank were 200-260 mW, 80-100 mW, and 10 mW, respectively.

  • https://doi.org/10.1016/j.net.2018.01.010 인용 PDF KSCI

The Conceptual Design of Primary Cooling System for an Advanced Research Reactor (수출전략형 연구로의 1차 냉각계통 개념설계)

  • Park, Yong-Chul;Kim, Kyung-Ryun
    • 유체기계공업학회:학술대회논문집
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    • 2005.12a
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    • pp.503-508
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    • 2005

  • An advanced Research Reactor (ARR) consists of an open-tank-type reactor assembly within a light water pool and generates thermal power of 20 MW. The thermal power is including a fission heat in the core, a fuel generated heat temporary stored in the pool, a circulating pumps generated heat and a neutron reflecting heat in the reflector vessel of the reactor. In order to remove the heat load, the primary cooling system will be installed. In this study, the conceptual design of the primary cooling system has been carried out using a design methodology of HANARO within a permissible range of safety. As results, it has been established that the conceptual design of the primary cooling system including design requirements, performance requirements, design restrictions, system descriptions and system operation to maintain the system functions.

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