• Proceedings of the SAREK Conference
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• 2008.06a
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• pp.1332-1337
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• 2008

Fire model shall be verified and validated to reliably predict the consequences of fires within its limitations. This study aims to predict pool fire with two rooms using FDS and to coompare FDS simulation results with PRISME experimental data which can be applicable to the fire of nuclear power plant facility. Four different sizes of grid (0.08m, 0.1m, 0.125m, 0.2m) are used in the simulation and the simulated results of specific quantities such as temperature, chemical composition, heat flux and heat release rate are compared to the experimental data. From this study, the FDS simulation results with the finer grid resolution show better similarity and trend with pool fire experimental data. The sensitivity analysis and the selection of the proper size grid are essential to predict the consequences of pool fire with two rooms reliably.

• Journal of the Society of Naval Architects of Korea
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• v.51 no.5
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• pp.388-395
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• 2014

This paper presents a method that generates alternatives of spatial arrangement for naval ships with limited information. To attain this end, GA (General Arrangement) methodology and GA reports of existing naval ships are analyzed. In order to improve the current naval ship spatial arrangement method that relies on the experience and know-hows of designers, we propose a systematic spatial arrangement process using SLP (Systematic Layout Planning), which determines relative positions of the components by analyzing relationships among them. The proposed method, along with the GA process, is applied to a virtual naval ship and layout alternatives are generated to verify usefulness of the method.

• Proceedings of the Korea Institute of Fire Science and Engineering Conference
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• 2010.10a
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• pp.241-245
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• 2010

화재방호에 성능기반 개념을 도입함에 따라 화재모델링의 활용도는 점점 높아지고 있다. 본 연구의 목적은 FDS를 이용하여 원자력발전소 펌프실의 윤활유 화재 시 케이블의 손상여부를 평가하고, 확인분석을 통해 화재모델링의 적합성을 파악하는 데 있다. 화재는 펌프 주변의 누출된 윤활유에서 발생하며 화원의 면적은 $2.75m^2$이고 단위면적당 열방출율은 $1,794kW/m^2$로 가정하였다. 계산결과, 고온기체층의 온도는 $400^{\circ}C$를 상회하고 있으나 케이블 트레이의 온도는 $50^{\circ}C$ 아래로 예측되고 있어 본 화재시나리오에서 케이블의 건전성은 유지되고 있으며 밀폐된 격실에서의 대형화재는 환기지배형 화재가 된다는 것을 보여주고 있다. 또한 확인분석 결과, 화재 시나리오의 주요 변수인 열방출율, 격실크기 그리고 강제 환기 변수가 확인계산 범위 내에 있어 본 계산결과는 NUREG-1824의 확인요건을 만족하고 있다. 따라서 펌프실 윤활유 화재에 대한 모델링의 적합성을 확인하였다.

• Journal of the Korea Institute of Building Construction
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• v.20 no.3
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• pp.279-287
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• 2020

Recently, the demand for underground-type ammunition storage facilities has increased. Comparing with a ground-type ammunition storage facility, the underground-type ammunition storage facility can decrease the standard of safety distance because fragment and blast wave can be locked in the rock formation. However, the absence of a design method on the underground-type ammunition storage chamber became a major setback for the construction promotion. In this study, the process for designing an overall configuration of the underground-type ammunition storage facility was provided. First, the determination method for configuration and number of the chamber was developed by performing the ammunition storage simulation. Then, a tunnel (i.e., transfer channel for vehicles) and designed chambers can be arranged on the basis of safety distance standard. The safety distance standard also should be considered for determining the location and the size of entrances because of the blast wave and fragment effect at the entrances when an explosion is generated inside a chamber. In addition, considerations on the design for the waterproof and the drainage of subsurface water were analyzed through construction cases. Finally, an example of designing underground-type ammunition storage chambers was provided in order to verify the developed design process.

• Proceedings of the Korean Nuclear Society Conference
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• 1996.05b
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• pp.616-621
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• 1996

PWR 원전의 중대사고시 격납건물내 수소거동을 모의한 NUPEC의 수소분포실험 결과를 MELCOR 1.8.3 코드를 이용하여 검증 차원의 비교분석을 수행하였다. 이 연구에서는 정확한 실험조건 및 코드의 특성을 반영하여 실험에서의 유동 및 열역학적 조건을 모두 모의하였다. 이를 통해 실험에서 나타난 수소거동 특성을 재확인하고, MELCOR 코드의 분석능력 및 특성을 평가하였다. ISP-35에 대한 비교분석을 통해 다격실 격납건물내 중대 사고시 수소 혼합 및 분포 현상에 대한 MELCOR의 분석능력을 확인하였다.

• Journal of Radiation Protection and Research
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• v.29 no.2
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• pp.117-127
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• 2004

A dynamic compartment model was developed to evaluate the transport of accidently released radionuclides onto rice-fields. In the model, the surface water compartment and shoot-base absorption were introduced to account for the effect of irrigation, which is essential to a rice cultivation. The soil mixing by plough and irrigation before transplanting rice was also considered, and the rate of root-uptake and shoot-base absorption were modeled in terms of the function of biomass. In order to test the validation of the model, it was applied to the analysis of some simulated $^{137}Cs$ deposition experiments that were performed while cultivating rice in a greenhouse using soils sampled from rice-fields around Kori, Yonggwang and Ulchin nuclear power plants. The model prediction was generally agreed within about one order of magnitude with experimental data.

• Journal of Radiation Protection and Research
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• v.19 no.1
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• pp.69-80
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• 1994

The TCMI(Three-Compartment Model for iodine) computer code has been developed, which is based on the three-compartment model and the respiratory model recommended in ICRP publication 54. This code is able to evaluate the thyroid burden, dose equivalent, committed dose equivalent and urinary excretion rate as time-dependent functions from the input data: working time and the radioiodine concentration in air. Using the TCMI code, the time-dependent thyroid burdens, the thyroid doses and the urinary excretion rates were calculated for three specific exposure patterns : acute, chronic and periodic. Applicability as an internal dose evaluation method has been assessed by comparing the results with some operational experiences. Simple equations and tables are provided to be used in the evaluation of the thyroid burden and the resulting doses for given I-131 concentration in air and the working time.

• Journal of Radiation Protection and Research
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• v.28 no.1
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• pp.1-8
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• 2003

The periodic safety review of operational nuclear power plants requires that the plants should keep a well organized environmental monitoring program. The past records of environment monitoring data were analyzed. and the tritium concentrations of the samples in the surface and ground water around Kori site were measured. It was shown that the tritium concentrations around the Kori site were slightly higher than that of natural background. The change of background tritium concentration was estimated through a numerical modeling. Two different versions of 7 compartments model - the world and the northern hemisphere - defined in NCRP-62 were modeled for the global tritium cycling. The numerical solution of the model was obtained using a computer program, AMBER. The four cases of tritium source-terms into the atmosphere were considered. The results showed that the tritium concentration in the surface soil water was higher than that in sea water or surface stream water. Also, it was shown that the tritium produced by the interaction between cosmic rays and the gases were the major source of tritium, and the tritium produced by nuclear weapon test decreased considerably.

• Proceedings of the Korea Institute of Fire Science and Engineering Conference
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• 2008.11a
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• pp.444-449
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• 2008

Fire model shall be verified and validated to reliably predict the consequences of fires within its limitations. This study aims to predict pool fire phenomena with two rooms using CFAST and to compare CFAST simulation results with PRISME experimental data which can be applicable to the fire of nuclear power plant facility. Five different mass loss rate(MLR) are used in the simulation and the simulated results of specific quantities such as temperature, chemical composition are compared to the experimental data. From this study, the CFAST simulation results with the proper MLR show better similarity and trend with pool fire experimental data.

• Proceedings of the Korea Institute of Fire Science and Engineering Conference
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• 2008.11a
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• pp.438-443
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• 2008

Fire model shall be verified and validated to reliably show the predictive capabilities for a specific use. In the process of model verification and validation, both the acceptable uses and limitation of fire model are established. In this study, the results of FDS simulation are compared with the data of PRISME experiment such as temperature, heat release rate, heat flux, product concentrations in the under-ventilated two-room condition. Furthermore, the sensitivity of FDS under ventilation condition changes are evaluated. FDS provide the reliable prediction for under-ventilated two-room fire scenario with slightly deviation.