• Title/Summary/Keyword: 연소용기

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Radiation Shielding Analysis of CANDU Spent Fuel Transport Cask (CANDU 사용후핵연료 수송용기 방사선차폐 영향평가)

  • Choi, Jong-Rak;Yoon, Jung-Hyun;Kang, Hee-Young;Lee, Heung-Young;Chung, Sung-Whan
    • Journal of Radiation Protection and Research
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    • v.18 no.2
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    • pp.27-35
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    • 1993
  • A shielding analysis of the shipping cask for transporting the CANDU spent fuel bundles has been studied. Radiation source term has been calculated on spent fuel with burn-up of 7,800 MWD/MTU and 5 years cooling time by ORIGEN2 code. The shielding calculation for the cask capable of transporting 378 bundles of CANDU spent fuel has been made by use of 1-D ANISN and 2-D DOT 4.2 codes. As a result of analysis, the optimum shield thickness of cask was obtained. And it is proved that the safety in radiation shielding under normal transport and hypothetical accident conditions is confirmed to satisfy the allowable values specified in IAEA Safety Series No. 6 and the Korean Atomic Law.

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Fire Hazard of PP and LLDPE dust in Chemical Plant Process (석유화학플랜트에서 발생하는 PP(Poly Propylene) 및 LLDPE(Linear Low Density Poly Ethylene) 분진의 연소 위험성에 관한 연구)

  • 김정환;이창우;현성호;권경옥
    • Fire Science and Engineering
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    • v.15 no.1
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    • pp.16-22
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    • 2001
  • Thermal properties of PP and LLDPE dusts from chemical plant and their risks of coexisting with oxidizer were investigated by a pressure vessel. The thermal decomposition of PP and LLDPE dusts with temperature using DSC and the weight loss with temperature using TGA were also investigated to find the thermal hazard of PP and LLDPE dusts. Using the pressure vessel which can estimate ignition and explosion of PP and LLDPE dusts coexisting with oxidizer, a series of bursting of a rupture disc, experiments has been conducted by varying the orifice diameters the weight ratio of the sample coexisting with oxidizers and the species of oxidizer. And fire gases was measured by gas analyser ($ECOM-A^+$). According to the results of the thermal analysis of PP and LLDPE dusts, the decomposition temperature range of PP and LLDPE dusts was 200 to 350 and 300 to $500^{\circ}c$, respectively. The risk of PP and LLDPE dusts coexisting with oxidizer was increased as the orifice diameter was decreased. On the other hand, it was increased as the weight ratio of the sample to the oxidizer were increased. In addition, the risk of PP and LLDPE dusts coexisting with oxidizer was affected by the decomposition temperature of the sample and oxidizer. It is found that the risk of fire becomes high when the decomposition temperature of the sample is about same as that of oxidizer. Also, the fire gases was occurred carbon monoxide and carbon dioxide. The amount of carbon monoxide generated was found to be much higher in PP decomposition than in LLDPE due to incomplete combustion of PP which has high content of carbon in chemical compound.

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Comparison of Forming force on forward and Backward Flow Forming for Combustion Chamber (연소기를 위한 전후방 유동성형에서의 성형력 비교)

  • Nam, Kyoun-Go;Cho, Cheon-Hwey;Hong, Sung-In
    • Journal of the Korean Society of Propulsion Engineers
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    • v.10 no.4
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    • pp.34-39
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    • 2006
  • The flow forming has been used to produce long thin walled tube parts, with reduced forming force and enhanced mechanical for a good finished part, compared with other method formed parts. Especially, the flow forming is suitable for making high precision thin walled cylinders, such as rocket motor cases, combustion chamber, hydraulic cylinders and high-pressure vessels and so on. In this paper, finite element analysis of three-roller forward and backward flow forming for combustion chamber is carried out to study effects of forming depth and feed rate on forming force. The axial and radial forming forces of forward flow forming on several forming depth and feed rate conditions are compared with those of backward flow forming.

사용후핵연료 장기 건식저장시 최대 초기저장 허용온도에 관한 연구

  • 박근일;이후근;변기호;노성기;박현수
    • Proceedings of the Korean Nuclear Society Conference
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    • 1996.05c
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    • pp.470-475
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    • 1996
  • 사용후핵연료 장기 건식저장시 여러가지 저장조건에서 사용후핵연료 피복관 및 사용후핵연료 ($UO_2$)에 대한 장기 건전성을 종합적으로 평가할 수 있는 SIECO 코드를 개발하였다. 건식저장 시스템은 사용후핵연료를 헬륨 및 공기분위기하에서 TN-24P 건식 저장용기에 장기 저장할 경우로 하였으며 피복관의 최대 표면온도는 COBRA-SFS코드를 사용하여 계산하였고, 열유동 해석결과를 바탕으로 SIECO코드를 이용하여 핵연료 연소도 및 냉각기간, 냉각매체에 따른 최대 건식저장 허용온도를 피복관의 열화 및 $UO_2$ 산화의 관점에서 계산하였다.

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압력용기에서의 중성자 조사량 평가 및 감소방안 연구

  • 김동규;김명현
    • Proceedings of the Korean Nuclear Society Conference
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    • 1997.10a
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    • pp.103-108
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    • 1997
  • 압력용기로의 속중성자 조사량 평가를 4군 노달 노심해석코드로 수행하였다. 이 코드는 MCNP에 비해 정확성은 떨어지나, 핵연료 연소의 효과나 핵연료 장전 모형의 영향을 쉽게 고려할 수 있었다. 속중성자 조사량 감소 방안으로서 반사체 차폐 구조물을 설치하는 방안과 노심외곽에 대체 핵연료 집합체를 장전하는 방안을 비교하였다. 신형원전의 경우 가장 효과적인 방안은 물 반사체 영역에 금속 차폐 구조물을 설치하는 것이나 운전중인 원자로의 경우 비록 주기길이의 감소와 핵연료 비용의 증가는 있으나 속중성자 감소 효과에 있어서는 대체 핵연료 집합체의 장전이 대안일 수 있다.

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산불로 인한 해양 환경 오염원에 대한 미역(Undaria pinnatifida)의 활력 측정

  • 강세은;최재석;홍용기
    • Proceedings of the Korean Society of Fisheries Technology Conference
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    • 2001.05a
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    • pp.203-204
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    • 2001
  • 산불의 발생은 산림 내에서 낙엽, 낙지, 초류, 임목 들의 연소로서 산불재 및 질소, 인 ,칼륨 등의 식물 영양염류와 토사 등이 산지에서 이탈되어 하천으로 쉽게 유입될 수 있으며, 산지와 해양이 인접한 지형에서는 하천에서의 자정작용 없이 곧바로 해양으로 유출되어 해양생물의 생태계에 직접 영향을 미칠 수도 있다. 해양 생태계에서는 하천의 오염원 유입으로 인하여 일차적으로 강 하구의 고착생물 즉 해조류들에 영향을 줌으로써 해양환경 오염에 대한 indicator 생물로서 이들 해조류를 많이 이용하고 있다. (중략)

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A Verification of Tip-over Analysis of a Dry Concrete Storage Cask under The Accident Conditions by a Test for the 1/3 Scale Model (사고조건하의 건식저장용기 전복해석검증을 위한 1/3 축소모델의 시험)

  • Kim Dong-Hak;Seo Ki-seog;Lee Ju-Chan;Jung Ki-Jung;Cho Chun-Hyung;Choi Byung-Il;Lee Heung-Young
    • Proceedings of the Korean Radioactive Waste Society Conference
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    • 2005.11a
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    • pp.237-246
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    • 2005
  • A tip-over test of the 1/3 scale model is conducted to verify the tip-oner analysis of a dry concrete storage cask under a hypothetical accident condition. The tip-oner analysis is executed using the velocity at each point which are determined from the initial angular velocity as the initial conditions of the model just before the impact. To confirm the structural integrity of the canister of a dry concrete storage cask, the non-detective testing such as Liquid Penetrants testing and Ultrasonic Testing are conducted. The strains and tile accelerations acquired by the tip-over test are compared with those by the analysis to verify the tip-over analysis. The lid of a storage calk are plastically deformed at the impact point. Liquid

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Water Vapor Transmission for T800/AD6005 Based Composite Motor Case (T800/AD6005계 복합재 연소관의 습기 투과에 관한 연구)

  • 박명규;류백능;최영보;도영대
    • Journal of the Korean Society of Propulsion Engineers
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    • v.2 no.1
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    • pp.50-58
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    • 1998
  • Water vapor transmission was tested in water bath controlled by $20^{\cire}C$, 90%RH for T800/AD6005 based composite motor case which made by filament winding method. We detected internal relative humidity of composite motor case by inserting the humidity detector through the head of motor case for the study of humidity transmission through the wall of composite motor case. We found out that this composite material appears the water vapor flux of 2.88${\times}$$10^{-9}$g/$\textrm{m}^2$sec and diffusivity of 7.98${\times}$$10^{-7}$$\textrm{mm}^2$/sec at $20^{\cire}C$, 90%RH water vapor condition.

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Thermal Analysis on the Spent Fuel Shipping Cask for a PWR Fuel Assembly (PWR 사용후 핵연료 수송용기에 대한 열해석)

  • Hee Yung Kang;Eun Ho Kwack;Byung Jin Son
    • Nuclear Engineering and Technology
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    • v.15 no.4
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    • pp.248-255
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    • 1983
  • The thermal analysis on the spent fuel shipping cask for a PWR fuel assembly is performed. Under the normal and fire-accident conditions the temperature distribution through a multilayer cask calculated in compliance with 10 CFR Part 71. A KNU 5&6 spent fuel assembly is assumed to be the decay heat source, which has the maximum discharge turnup of 45, 000MWD/MTU and has been stored in the spent fuel storage pool for 300 days. As a result of thermal analysis, the maximum cladding temperature in case of dry cavity under fire-accident conditions is calculated to be 455$^{\circ}C$. This value is much less than the limiting value specified in 10 CFR Part 50.46. It indicates that no fuel rod cladding rupture could occur under fire-accident conditions. It was also found that no melting of lead would take place in the major shield region.

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Evaluation of the Aging Effects on the Performance of the Pyrotechnic Igniter (파이로 테크닉 점화기의 노화 성능 평가)

  • 장승교;류병태
    • Journal of the Korean Society of Propulsion Engineers
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    • v.1 no.2
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    • pp.91-102
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    • 1997
  • In order to evaluate the effects of aging on the ignition performance, pyrotechnic igniters were separated from twelve-year-old, fifteen-year-old, and sixteen-year-old live rocket motors. The characteristic values of the ignition material were measured, and the firing tests of the igniters were performed. The moisture content, the outer dimension, the crush strength, the thermal decomposition characteristics, and the heat of formation the B/$KNO_3$ ignition pellet were measured. The crush strength was increased and the heat of formation was reduced as aged, but no change was detected for other characteristic values. The burning test results of the igniter pellet in the closed bomb and the inert motor showed that the burning rate of the ignition pellet was increased by 10%, and the integration of pressure $P_t$ of the p-t curve was reduced by 15% for aged samples. It was inferred that the burning rate was increased as the crack was appeared in the pellet and $P_t$ could be proportionally decreased with the heat of explosion.

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