• Title/Summary/Keyword: 격실

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격납용기내 소격실에서의 수소혼합 연구

  • 박군철;최용석;이운장
    • Proceedings of the Korean Nuclear Society Conference
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    • 1997.05a
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    • pp.617-622
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    • 1997
  • 격납건물내 소격실에서의 수소혼합 정도를 파악하고 격실내 균일한 혼합을 좌우하는 인자의 영향을 분석하기 위하여 소규모 혼합실험을 수행했다. 본 연구에서는 해석적으로 수립된 3차원 혼합 모델의 검증을 위하여 3차원 모사가 가능하도록 실험 장치를 구성하였다. 격납용기 내에서 수소 생성의 주원인이 되는 노심으로부터의 수소거동을 분석하기 위한 기초 실험(실험 A)과 안전주입 탱크 격실에서의 수소거동을 분석하기 위해 원형 혼합 chamber를 구상했다. 기초실험 A에서는 혼합 chamber내 축 방향으로 대칭적인 오리피스형 장애물을 설치하고 실험했고 안전주입 탱크 격실을 모사한 실험 B는 영광 3&4호기를 바탕으로 축소시켜 안전주입탱크 격실내 존재하는 두충과 안전 주입 탱크 사이의 틀을 통한 혼합체의 거동을 분석했다. 실험결과 오리피스형 장애물을 설치한 기초실험에서는 원형 띠모양의 장애물이 혼합체의 거동에 큰 영향을 주지 않는 것이 관측됐지만 안전주입탱크격실 실험에서는 격실내 장애물로 존재하는 두충이 혼합체의 거동에 큰 영향을 주는 것이 관측됐다.

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A Study on the Reliability Improvement of Compartment Leak Test in Surface Vessels (함정 격실기밀 평가 방안에 대한 신뢰성 향상 연구)

  • Choi, Sang-Min;Park, Dong-Kyu;Beak, Yong-Kawn
    • Journal of the Korea Academia-Industrial cooperation Society
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    • v.21 no.4
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    • pp.546-551
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    • 2020
  • Generally, surface vessels have many compartments for operation and living quarters, and each compartment is an important space for the ship's survivability. During ship construction, a compartment leak test is necessary and is carried out on each vessel. However, the current test method is in doubt when looking at the actual test results. The reason is that only one pressure gauge is used for the measurement to check the air, so an uncomprehended phenomenon is detected during group compartment leak tests. From this point of view, an improved test device and method are needed. In this study, a multi-channel data acquisition device with multiple pressure sensors is proposed to detect each compartment's pressure variation or pressure drop. This test is a more confidential compartment leak test than the current method, and the test device can show real-time pressure detection values of each of the pressure sensors, which are installed in each compartment, including unmanned space.

Development of Pressure Correction System for Surface Vessel to Ensure Reliability of Compartment Test Result (수상함 격실기밀시험 결과의 신뢰성 확보를 위한 압력 보정 시스템 개발)

  • Min, Il-Hong;Kim, Jun-Woo;Son, Gi-Joong
    • Journal of the Korea Academia-Industrial cooperation Society
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    • v.22 no.1
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    • pp.409-414
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    • 2021
  • Tightness performance that blocks compartments is important for surface ships to achieve superior mission performance and survivability in combat environments. To meet the above requirements, airtightness of the structural elements and the appropriate strength to specific areas are checked during a test run after ship construction. In particular, air tests of compartments adjacent to the water surface are performed. In an air test, air is injected into the compartment up to the test pressure of the test memo. The pressure drop value is checked after 10 minutes to determine if the requirements of the corresponding area are satisfied. In summer, however, when the influence of the outside temperature is large, a phenomenon in which the internal pressure increases during the air test was identified. This phenomenon reduces the reliability of the test result. Therefore, a system was designed to compensate for temperature changes in the compartments through this study. The developed system calculates the amount of pressure change caused by a temperature change in the compartment and outputs a correction value. The pressure change was calculated using the ideal gas equation, reflecting the maintenance, increase, and decrease in temperature during the test process. A comparison of the calculated pressure correction value with the database of NIST REFPROP revealed a difference of 0.126% to a maximum of 0.253%.

The Effect of Obstacles in a Compartment on Personnel Injury Caused by Blast (격실 내 장애물이 폭압에 의한 인원 피해에 미치는 영향)

  • Park, Sung-Jun
    • Journal of the Korea Society for Simulation
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    • v.26 no.3
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    • pp.1-11
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    • 2017
  • Blast injuries in a compartment are investigated, and the effects of obstacles on blast injury are particularly analyzed by comparing injuries in the compartments with or without protruding obstacles inside. Even if blast pressure profile tends to be complicated in a confined space unlike in open field, it can be obtained in a relatively short time by using some empirical fast running models for simple confined spaces. However, a finite element method should be employed to obtain blast pressure profiles in a case with obstacles in confined spaces, because the obstacles heavily disturb blast waves. On the other hand, Axelsson SDOF(Single degree of freedom) model and ASII(Adjusted severity of injury index) injury level are employed to estimate blast injury in compartments, because the usual pressure-impulse injury criterion based on the ideal Friedlander waves in open the field cannot be applied to personnel in a confined space due to complexity of blast waves inside. In cases with obstacles, chest wall velocity was reduced by 26 to 76 percent(%) and the personnel injury in the compartment caused by blast was also reduced.

Zion 원전 Cavity 및 상부 격실에 대한 노심용융물 고압분출 실험 연구

  • 박래준;김상백;조영로;김희동
    • Proceedings of the Korean Nuclear Society Conference
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    • 1997.05a
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    • pp.563-568
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    • 1997
  • Zion원전의 cavity 및 상부 격실을 1/20로 선형 축소 모의하여 상부 격실에 의한 노심용융물 나포특성을 규명하기 위한 노심용융물 고압분출 실험 연구를 수행하였다. 본 연구에서는 원자로용기 외곽에 환형통로가 있는 경우와 없는 경우로 구분하여 원자로용기 파손 때의 용융물양, 파손 면적에 따라 원자로용기 압력면화에 대한 실험을 물과 질소기체를 이용하여 수행하였다. 실험결과 환형통로가 없는 경우는 대부분의 노심용융물이 상부 격실에 나포되었으나 환형통로가 있는 경우는 환형 통로를 통하여 많은 양이 방출되었다 환형 통로를 통한 용융물의 직접 방출은 격납용기 상부대기와 열전달이 직접 이루어지기 때문에 격납용기 직접가열 효과가 크게 나타날 수 있다. Cavity내 노심 용융물 방출분율은 원자로용기파손 때 용융물양보다는 파손면적의 영향이 더 크게 나타났다.

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Compartment Fire Test Using Kerosene and Aviation Fuel (등유 및 항공유를 사용한 격실 화재시험)

  • Bang, Kyoung-Sik;Lee, Ju-Chan;Seo, Chung-Seok;Seo, Ki-Seog;Kim, Hyung-Jin
    • Proceedings of the Korea Institute of Fire Science and Engineering Conference
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    • 2012.04a
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    • pp.476-479
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    • 2012
  • 차량의 충돌에 따른 등유의 누출에 의한 화재와 항공기 충돌에 따른 항공유의 누출에 의한 화재 발생 시 격실의 개구부 크기에 따른 화염온도를 평가하기 위해 화원으로 등유와 Jet-A-1을 사용하고 개구부의 크기를 조절해 가며 격실화재시험을 수행하였으며, 가장 높게 측정된 시험결과의 조건으로 과도화재시험을 수행하여 금속저장용기가 화염온도에 미치는 영향을 평가하였다. 시험결과 등유보다 Jet-A-1의 열 방출속도 및 질량 연소유속이 크게 나타났으며, Jet-A-1에서의 화염온도가 높게 측정되었다. 연료 소모율은 개구부의 크기가 클 경우 작은 경우보다 크게 나타났으며, 개구부의 크기가 클 경우 화염온도가 높게 측정되었다. 격실 내에 금속저장용기가 저장되었을 때는 저장용기가 화염으로부터 받는 열량만큼 화염의 온도는 낮아지는 것으로 나타났다.

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Calculation of the Minimum Charge Weight Required for 100% Personnel Target Lethality inside a Room with a Square Base (바닥 면이 정사각형인 격실 내 100% 인명피해를 위한 최소 화약량 산정)

  • Han, Minsung
    • Journal of the Korea Society for Simulation
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    • v.28 no.1
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    • pp.109-115
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    • 2019
  • The probability of lethality of personnel targets inside a room is a key issue at assessing effectiveness of a weapon system. In this study, the minimum charge weight to achieve 100% lethality of personnel targets inside a box-type room is proposed at each side length of a base of a room. A fast running blast wave model is used to simulate the pressure-time histories of the blast generated by an internal explosion inside a room, and Axelsson SP method is used to evaluate the lethality of personnel targets under the blast. 176 different internal explosion scenarios are simulated for cases of TNT weights ranging from 20kg to 170kg inside a room whose square base has a side length ranging from 5m to 15m. A linear model and a charge-density model were developed to predict the minimum charge weight to achieve 100% lethality inside a room given a length of a base of a room.

Analysis of Loss of HVAC for Nuclear Power Plant (원전의 공기조화설비(HVAC) 상실사고 분석방법)

  • Song, Dong-Soo
    • Journal of Energy Engineering
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    • v.23 no.1
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    • pp.90-94
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    • 2014
  • Environmental qualification (EQ) for safety-related equipment is required to ensure that those equipment will perform their required function even under the harsh environment conditions arising from design basis accident in the nuclear power plant. As a part of EQ program, the room temperature analysis in case of a loss of Heating, Ventilation, and Air Conditioning(HVAC) system was carried out to ensure the operability of the safety-related equipment of a nuclear power plant randomly chosen among the Korean nuclear power plants. In this paper, this analysis was performed in the conservative perspective using GOTHIC code. The room temperature analysis includes selecting the rooms in which the safety related equipment are located but not supported by safety related HVAC and determining the temperature of the selected rooms. Target rooms for the analysis consist of W229/W237 (Aux. feedwater pump room), W232 (Aux. feedwater tank room) and W230 (Equipment passageway). The results showed the temperature range from $43^{\circ}C$ to $83^{\circ}C$, in 72 hours after a loss of HVAC. Those values are far below of generic EQ temperature($171^{\circ}C$). Therefore, it is satisfied with EQ requirement of temperature limits on safety related equipment.

Heat-up Calculation for the Auxiliary Feed Water Pump Room at Ulchin Units 3 and 4 for Loss of HVAC Accidents (HVAC 상실사고시 울진원전 3/4 호기의 보조급수펌프 격실 온동상승 평가)

  • Yoon, Churl;Park, Jin-Hee;Hwang, Mee-Jeong;Han, Sang-Hoon
    • Transactions of the Korean Society of Mechanical Engineers B
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    • v.36 no.5
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    • pp.553-562
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    • 2012
  • Computational Fluid Dynamics (CFD) analysis has been performed to estimate the air temperature inside an Auxiliary Feed Water (AFW) Motor-Driven (MD) pump room for the case where there is loss of Heating, Ventilation, and Air-Conditioning (HVAC). A transient calculation for the closed pump room without cooling by any HVAC system shows that the volume-averaged air temperature reaches around $60^{\circ}C$ for a transient period of 8.0 h. From previous studies, the external air and surface boundary temperatures are assumed to increase slowly starting from an initial temperature of $35^{\circ}C$. For the cases where the door is opened at 2, 4, and 6 h after the initiation of HVAC failure, the average air temperature promptly drops by about $4^{\circ}C$ when the door is opened and then slowly increases. The current calculations based on the CFD technique predict the rate of increase of air temperature to be lower than that determined by previous conservative calculations on the basis of a lumped model.

Optimized Flooding Analysis Method for Compartment for Nuclear Power Plant (원전 격실에 대한 최적 침수분석 방법)

  • Song, Dong-Soo;Kim, Sang-Yeol
    • Journal of Energy Engineering
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    • v.21 no.1
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    • pp.75-80
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    • 2012
  • In this paper a realistic bounding method for flooding analysis following rupture of large size of thanks and piping is defined. Mass and energy release during main feedwater line break accident is analyzed with RETRAN code. It is modeled that the main feed water control valve is closed in 5.0 seconds after reactor trip. In result of the analysis, largest mass and energy is discharged at 70% reactor power. The flood sources for main feedwater room are calculated when piping failure occurs in the high energy line and medium energy line. Based on the result of flood level (1.43m), it is investigated that all of the safety-related environmental qualification equipments are well located above the flood level.