• Title/Summary/Keyword: Canister

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Thermal Stress Analysis of Spent Nuclear Fuel Disposal Canister (심지층 고준위 핵폐기물 처분용기의 열응력 해석)

  • 하준용;권영주;최종원
    • Proceedings of the Korean Society of Precision Engineering Conference
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    • 1997.10a
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    • pp.617-620
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    • 1997
  • In this paper, the thermal stress analysis of spent nuclear fuel disposal canister in a deep repository at 500m underground is done for the underground pressure variation. Since the nuclear fuel disposal usually emits much heat and radiation, its careful treatment is required. And so a long term safe repository at a deep bedrock is used. Under this situation, the canister experiences some mechanical external loads such as hydrostatic pressure of underground water, swelling pressure of bentonite buffer, and the thermal load due to the heat generation of spent nuclear fuel in the basket etc.. Hence, the canister should be designed to designed to withstand these loads. In this paper, the thermal stress analysis is done using the finite element analysis code, NISA.

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Three-Dimensional Fluid Flow Analysis of Automotive Carbon Canister for Reducing Evaporative Emissions (증발가스 배출물 억제를 위한 자동차용 캐니스터의 3차원 유동장 해석)

  • 정수진;김우승
    • Transactions of the Korean Society of Automotive Engineers
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    • v.9 no.6
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    • pp.85-93
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    • 2001
  • Minimized canister flow restriction and maximized flow uniformity are desired to maximize a purge capability. With the impending ORVR(On Board Refueling Vapor Recovery) systems, the reduction of restriction and increase of flow uniformity in a carbon canister becomes even more critical to meet the stringent regulation. In this study, three-dimensional numerical simulations have been performed to investigate the three-dimensional internal flow patterns in a carbon canister during purge. The effects of the declined angle of the purge pipe and the number of partitions on the pressure drop and purge efficiency in a carbon packed bed are examined. Results show that the purge efficiency and space velocity distribution are affected in the upstream region of 40% of total canister bed by porosity of carbon granule and angle of purge pipe. It is also found that the purge efficiency decreases with increasing the number of partitions.

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The Effect of Pyro Shock on Canister with Composite Sandwich Panel (복합재 샌드위치 패널 발사관의 폭발충격 영향도 분석)

  • Choi, Wonhong
    • Transactions of the Korean Society for Noise and Vibration Engineering
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    • v.26 no.6_spc
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    • pp.667-673
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    • 2016
  • Canister with composite sandwich panel has been suggested owing to its higher stiffness and strength over a weight for square shaped canisters. The pyro shock induced by a short time explosion inside a canister is generally considered to be the most severe source of load affecting on the entire structure. Therefore, in this study, the approach and modeling method to identify the effect of pyro shock on canister with composite sandwich panel in a numerical way were mainly discussed. Moreover, the verification was implemented through comparison with test results.

ACTIVATED CARBON CANISTER PERFORMANCE FOR A SPARK IGNITION ENGINE

  • CHOI G. H.;CHOI K. S.;CHUNG Y. J.;KIM I. M.;DIBBLE R. W.;HAN S. B.
    • International Journal of Automotive Technology
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    • v.7 no.1
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    • pp.9-15
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    • 2006
  • Prediction of the performance of a carbon canister in vehicle evaporative emission control system has become an important aspect of overall fuel system development and design. A vehicle's evaporative emission control system is continuously working, even when the vehicle is not running, due to generation of vapors from the fuel tank during ambient temperature variations. Evaporative emissions from gasoline powered vehicles continue to be a major concern. The objective of this paper is to clarity the flow characteristics and other such fundamental data for the canister during loading and purging are needed, and this data will prove valuable in the development of the canister. This paper is to evaluate the relationship between carbon canister condition and engine performance during engine operation, and the effects of evaporative emissions on the engine performance were investigated.

Structural Analysis of PWR(pressurized water reactor) Canister for Applied Impact Force Occurring at the Moment of Falling Plumb Down Collision (추락낙하 충돌 시 가해지는 충격에 대한 경수로(PWR) 처분용기의 구조해석)

  • Kwon, Young-Joo
    • Journal of the Computational Structural Engineering Institute of Korea
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    • v.24 no.2
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    • pp.211-222
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    • 2011
  • In this paper a structural analysis of the PWR(pressurized water reactor) canister with 102cm diameter is carried out to evaluate the structural safety of the canister for the impact force occurring at the moment of collision with the ground in the falling plumb down accident from the carriage vehicle which may happen during the canister handling at the spent nuclear fuel disposal repository. For this, a rigid body dynamic analysis of the canister is executed to compute the impact force using the commercial CAE system, RecurDyn, and a nonlinear structural analysis is performed to compute stresses and deformations occurring inside the canister for this computed impact force using the commercial FEM code, NISA. From these analysis results, the structural safety of the canister is evaluated for the falling plumb down accident from the carriage vehicle due to the inattention during the canister handling at the repository. The rigid body dynamic analysis performed assuming the canister as a rigid body shows that the canister falls plumb down to the ground in two types. And also it shows that early collision impact force is the biggest one and following impact forces decrease gradually. The height of the carriage vehicle in the repository is assumed as 5m in order to obtain the stable structural safety evaluation result. The nonlinear structural analysis of the canister is executed for the biggest early impact force. The structural analysis result of the canister shows that the structural safety of the PWR canister is not secured for the falling plumb down accident from the moving carriage vehicle because the maximum stresses occurring in the cast iron insert of canister are bigger than the yield stress of the cast iron.

A Structural Analysis of the Spent Nuclear Fuel Disposal Canister with the Spent Nuclear Fuel Basket Array Change for the Pressurized Water Reactor(PWR) (고준위폐기물 다발의 배열구조변화에 따른 가압경수로(PWR)용 고준위폐기물 처분용기의 구조해석)

  • Kwon, Young-Joo
    • Journal of the Computational Structural Engineering Institute of Korea
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    • v.23 no.3
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    • pp.289-301
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    • 2010
  • A structural model of the SNF(spent nuclear fuel) disposal canister for the PWR(pressurized water reactor) for about 10,000 years long term deposition at a 500m deep granitic bedrock repository has been developed through various structural safety evaluations. The SNF disposal baskets of this canister model have the array type of which four square cross section baskets stand parallel to each other and symmetrically with respect to the center of the canister section. However whether this developed structural model of the SNF disposal canister is best is not determinable yet, because the SNF disposal canister with this parallel array has a limitation in shortening the diameter for the weight reduction due to the shortest distance between the outer corner of the square section and the outer shell. Therefore, the structural safety evaluation of the SNF disposal canister with the rotated basket array which is also symmetric with respect to the canister center planes is very necessary. Even though such a canister model has not been found as yet in the literature, the structural analysis of the canister with the rotated basket array for the PWR is required for the comparative study of the structural safety of canister models. Hence, the structural analysis of the canister with the rotated basket array in which each basket is rotated with a certain amount of degrees around the center of the basket itself and arrayed symmetrically with respect to the center planes is carried out in this paper. The structural analysis result shows that the SNF disposal canister with the rotated basket array in which the SNF disposal basket is rotated as 30~35 degrees around the center of the basket itself is structurally more stable than the previously developed SNF disposal canister with the parallel basket array.

Rigid Body Dynamic Analysis on the Spent Nuclear Fuel Disposal Canister under Accidental Drop and Impact to the Ground: Numerical analysis (사고로 지면으로 추락낙하 충돌하는 고준위폐기물 처분용기에 대한 기구동역학 해석: 수치해석)

  • Kwon, Young-Joo
    • Journal of the Computational Structural Engineering Institute of Korea
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    • v.26 no.5
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    • pp.373-384
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    • 2013
  • This paper is the second paper among two papers which constitute the paper about the rigid body dynamic analysis on the spent nuclear fuel disposal canister under accidental drop and impact to the ground. This paper performed the numerical study on the rigid body dynamic analysis. Through this study the impulsive force which is occurring in the spent nuclear fuel disposal canister under accidental drop and impact to the ground and required for the structural safety design of the canister is computed numerically. The main content of this numerical study is about the technical method how to compute the impulsive forces occurring in the canister under accidental drop and impact to the ground by using the commercial rigid body dynamic analysis computer codes. On the basis of this study the impulsive force which is occurring in the canister in the case of collision with the ground is numerically computed. This numerically computed impulsive force is increasing as the canister weight is increasing, and the canister falls plumb down and collides with the ground in three types according to the analysis results.

A Study on the Hydrogen Supply for Variation in Output from a Metal Hydride Canister (금속수소화물 금속용기로부터 출력변동에 필요한 수소공급에 관한 연구)

  • Jung, Young-Guan;Kim, Se-Woong;Kim, Kyung-Hoon;Choi, Seong-Dae;Jang, Tae-Ik;Hwang, Chul-Min
    • Transactions of the Korean hydrogen and new energy society
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    • v.20 no.3
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    • pp.216-223
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    • 2009
  • The relation between temperature and hydrogen desorption on variation in output was investigated for the metal hydride canister. For this study, an AB$_5$ type alloy were chosen as a hydrogen storage material in the metal hydride canister. And application to the single proton exchange membrane fuel cell was evaluated. As the results, the hydrogen desorption was linearly increased as the temperature was risen. In addition, metal hydride canister heating was able to correspond the variation of load as power request in the PEMFC system.

RAM(Rolling Airframe missile) Canister Localization on development of technical process and Quality Assurance procedure establishment (RAM(Rolling Airframe Missile) 발사관 국산화에 대한 공정 기술 개발 및 품질 인증 절차 확립)

  • Lee, Sang-Woo;Jo, Jung-Pyo;Lee, Sang-Jae
    • Proceedings of the Korean Society of Propulsion Engineers Conference
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    • 2010.11a
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    • pp.541-547
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    • 2010
  • This document presents the research and result about localization of the fiber-based launching canister of rolling missile which has helical rails. This document is about the technical process development which is included with the manufacturing of helical rails and application of the flame spaying which is different with other the fiber-based launching canister in korea. and And this document is about quality Assurance procedure through the qualification test and structural evaluation in conditions that the canister has to have in real shipboard environment.

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AN ANALYSIS OF THE THERMAL AND MECHANICAL BEHAVIOR OF ENGINEERED BARRIERS IN A HIGH-LEVEL RADIOACTIVE WASTE REPOSITORY

  • Kwon, S.;Cho, W.J.;Lee, J.O.
    • Nuclear Engineering and Technology
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    • v.45 no.1
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    • pp.41-52
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    • 2013
  • Adequate design of engineered barriers, including canister, buffer and backfill, is important for the safe disposal of high-level radioactive waste. Three-dimensional computer simulations were carried out under different condition to examine the thermal and mechanical behavior of engineered barriers and rock mass. The research looked at five areas of importance, the effect of the swelling pressure, water content of buffer, density of compacted bentonite, emplacement type and the selection of failure criteria. The results highlighted the need to consider tensile stress in the outer shell of a canister due to thermal expansion of the canister and the swelling pressure from the buffer for a more reliable design of an underground repository system. In addition, an adequate failure criterion should be used for the buffer and backfill.