• 제목/요약/키워드: Fuel transport

검색결과 637건 처리시간 0.021초

Structural integrity of KJRR-F fresh nuclear fuel under vehicle-induced vibration for normal transport condition

  • Jeong, Gil-Eon;Yang, Yun-Young;Bang, Kyoung-Sik
    • Nuclear Engineering and Technology
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    • 제54권4호
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    • pp.1355-1362
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    • 2022
  • Nuclear fuel, including its fresh state, must be handled safely due to its critical and hazardous nature. Under normal transport conditions, several interactions take place among different components, such as transport cask used for loading the nuclear fuel and tie-down structure to attach with the vehicle. To ensure structural integrity of the nuclear fuel, vibrations and impacts transmitted from the vehicle must be sufficiently reduced. Therefore, in this study, we conducted two transportation tests from Daejeon to Kijang in Korea to verify the vehicle-induced vibrational characteristics of the KJRR-F fresh nuclear fuel when transported under normal transport conditions. The speed and location of the vehicle were obtained via GPS, and the accelerations between the vehicle and the KJRR-F fresh nuclear fuel were measured. Additionally, using the acceleration results, a structural analysis was conducted to confirm the structural integrity of the nuclear fuel under the most severe conditions during normal transport.

KN-12 운반용기를 이용한 고리 사용후핵연료 소내수송.저장 (On-Site Transport and Storage of Spent Nuclear Fuel at Kori NPP by KN-12 Transport Cask)

  • 정성환;백창열;최병일;양계형;이대기
    • 방사성폐기물학회지
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    • 제4권1호
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    • pp.51-58
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    • 2006
  • 고리 원전 사용후핵연료 저장조의 저장용량을 확보하기 위하여 2002년부터 사용후핵연료 운반용기를 이용하여 400다발 이상의 PWR 사용후핵연료 집합체를 원전부지 내에 수송, 저장하였다. 이를 위하여 KN-12 운반용기, 관련장비 및 수송차량으로 구성되는 수송시스템을 구성하였다. KN-12 운반용기는 국내 원자력법 및 IAEA의 수송규정에 따라 설계, 제작되고, 정부로부터 인허가를 획득하였으며, 취급장비 역시 관련규정에 따라 구비하였다. 수송 저장작업은 2 대의 운반용기를 동시에 투입하여 수행하였으며, 모든 작업공정에 대하여 엄격한 품질관리 및 방사선 안전관리를 수행하여 수송 안전성을 확보하고 신뢰도를 제고하였다.

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흡기포트 분사방식의 가솔린 엔진에서 급가속시 연료 거동에 관한 연구 (A Study on Fuel Transport Characteristics in a Port Fuel Injected Sl Engine during Transient Condition)

  • 황승환;조용석;이종화
    • 한국자동차공학회논문집
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    • 제11권3호
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    • pp.20-27
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    • 2003
  • In this paper, the fuel transport characteristics during transient condition was studied by using a Fast Response Flame Ionization Detector(FRFID). The quantitative measurement method for the inducted fuel mass into cylinder is studied. The inducted fuel mass into the cylinder was estimated by using calculated air-fuel ratio by hydrocarbon concentration of cylinder and air flow model. In order to estimate the transportation of injected fuel from the intake port into cylinder, the wall wetting fuel model was used. The two coefficient $\alpha$,$\beta$) of the wall-wetting fuel model was determined from the measured fuel mass that was inducted into the cylinder at the first cycle after injection cut-off To reduce an air/fuel ratio fluctuation during rapid throttle opening, the appropriate fuel injection rate was obtain from the wall wetting model with empirical coefficients. Result of air/fuel ratio control, air/fuel excursion was reduced.

전기화학 반응에 의한 생성 열의 단순화된 처리 기법을 이용한 평판형 고체산화물 연료전지 내부의 이동현상에 대한 전산 해석 (Computational Analysis of Transport Phenomena in a Planar-Type Solid Oxide Fuel Cell with a Simplified Treatment of the Electrochemical Heat Generation)

  • 차훈;손정락;노승탁
    • 한국세라믹학회지
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    • 제42권12호
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    • pp.846-853
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    • 2005
  • For the performance prediction of a planar-type solid oxide fuel cell, the computational analysis of transport phenomena with a simplified treatment of heat generation by the electrochemical reaction is conducted. From the result of the computational analysis, it is shown that the electrochemical reaction is closely related to the transport phenomena inside a solid oxide fuel cell. Transport phenomena including heat and mass transfer influences on the distribution of local current density and, as a result, on the performance characteristics of the fuel cell. Computational analysis is also extended to the parametric study to investigate the performance behavior of the fuel cell with different amount of supplied fuel flow rates. It is also demonstrated that the mathematical formulation and computational procedures proposed in this study can be applied to prove the importance of the specific TPB area in the manufacturing process of electrodes in solid oxide fuel cells.

해외 신재생연료 의무혼합제도 비교분석 연구 (Study on Comparison of Nenewable Fuel Standard Policy on Global)

  • 임의순;김재곤;정충섭
    • 한국신재생에너지학회:학술대회논문집
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    • 한국신재생에너지학회 2011년도 추계학술대회 초록집
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    • pp.150.1-150.1
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    • 2011
  • The global rise of greenhouse gas(GHG) emissions and its potentially devastating consequences require a comprehensive regulatory framework for reducing emissions, including those from the transport sector. alternative fuels and technologies have been promoted as a means for reducing the carbon intensity of the transport sector. Renewable fuel policies were historically motivated by energy security concerns, and to promoted agricultural industries. In the last decade, biofuels have also been discussed as low or net-zero carbon soures of energy for transportation. Hence, the development of biofuels has been supported by a range of policy instruments, including volumetric targets or blending mandates, tax incentives or penalties, preferential government purchasing, government funded research, development in world-wide. As one of the most powerfuel instruments, renewable fuel mandates require fuel producers to produce a pre-defined amount(or share) of biofuels and blend them with petroleum fuel. In this study, we reviewed Renewable Fuel Standard(RFS, USA), Renewable Transport Fules Obligation (RTFO, UK) as a renewable fuel mandate policy to reduce GHG. This includes not only mandate system for blending of biofuels in transport fuels, but also sustainability to use biofuels in this system.

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CANFLEX 핵연료를 사용한 CANDU-6의 열수송계통 안정성 분석 (CANDU-6 Heat Transport System Stability Analysis With Canflex Fuel Bundle)

  • Shin, Jung-Cheol;Park, Ju-Hwan;Kim, Tae-Han;Suk, Ho-Chun
    • Nuclear Engineering and Technology
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    • 제27권3호
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    • pp.358-373
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    • 1995
  • 중수로용 개량핵 연료집합체인 CANFLEX 핵연료다발의 CANDU-6 원자로 장전시 열수송계통에 대한 유동안정성이 분석되었다. CANFLEX 핵연료다발은 기존의 37개봉 핵연료다발과 원자로출력 및 압력강하 측면에서 거의 일치되며, 이로인해 수력적 거동이 양립하는 반면, CANFLEX핵연료다발은 기존의 37개봉 핵연료다발 보다 임계채널 출력이 증가하며, 반경방향 출력분포의 평탄화로 인해 균일한 엔탈피 분포를 확보할 수 있게 된다. CANFLEX 핵연료다발 및 출구모관들의 상호연결관에 대한 SOPHT 모델을 개발하였으며, 이 모델을 이용하여 CANFLEX 핵연료다발이 장전된 월성 1호기의 유동 안정성 거동이 해석되었다. 해석결과, 열수송계통의 출구모관들의 상호연결관이 없을 경우에는 기존의 37개봉 핵연료다발과 같이 유동이 불안정함을 보였으며, 출구모관들의 상호연결관이 있을 경우에는 정격출력의 $\pm$1% 내에서 안정함을 보였다. 따라서 CANFLEX 핵연료다발의 월성 1호기 장전시 열수송계통의 유동안정성 측면에서는 건전할 것으로 판단되었다.

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Data analysis of simulated fuel-loaded sea transportation tests under normal conditions of transport

  • JaeHoon Lim;Woo-seok Choi
    • Nuclear Engineering and Technology
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    • 제56권2호
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    • pp.375-388
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    • 2024
  • In this study, to evaluate the shock and vibration load characteristics of used fuel, a sea transportation test was conducted using simulated fuel assemblies under normal transport conditions. An overall test data analysis was performed based on the measured strain and acceleration data obtained from cruise, rotation, acceleration, braking, depth of water, and rolling tests. In addition, shock response spectrum and power spectral densities were obtained for each test case. Amplification and attenuation characteristics were investigated based on the load path. The load was amplified as it passed from the overpack to the simulated used fuel-assembly. As a result of the RMS trend analysis, the fuel-loading position of the transportation package affected the measured strain in the fuel rod, and the maximum strains were obtained at the spans with large spacing. However, even these maximum strains were very small compared to the fatigue strength and the cladding yield strength. Moreover, the fuel rods located on the side exhibited a larger strain value than those at the center.

Multi-body dynamics model for spent nuclear fuel transportation system under normal transport test conditions

  • Seongji Han;Gil-Eon Jeong;Hyeonbeen Lee;Woo-Seok Choi;Jin-Gyun Kim
    • Nuclear Engineering and Technology
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    • 제55권11호
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    • pp.4125-4133
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    • 2023
  • The transportation of spent nuclear fuel is an important process that involves road and sea transport from an interim storage facility to storage and final disposal sites. As spent nuclear fuel poses a significant risk, carefully evaluating its vibration and shock characteristics under normal transport conditions is essential. In this regard, full-scale multi-modal transport tests (MMTT) have been conducted domestically and internationally. In this paper, we discuss the process of developing a multi-body dynamics (MBD) model to analytically simulate conditions that cannot be considered in tests. The MBD model is based on the KORAD-21 transportation system was validated using the Korean MMTT results from 2020 to 2021. This paper summarizes the details of the development and verification of the MBD model for the KORAD-21 transportation system under normal transport test conditions. This approach can be applicable to various transportation scenarios and systems, and the results of this study will help to ensure that nuclear fuel transportation is conducted safely and effectively.

Rolling Test Simulation of Sea Transport of Spent Nuclear Fuel Under Normal Transport Conditions

  • JaeHoon Lim;Woo-seok Choi
    • 방사성폐기물학회지
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    • 제21권4호
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    • pp.439-450
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    • 2023
  • In this study, the impact load resulting from collision with the fuel rods of surrogate spent nuclear fuel (SNF) assemblies was measured during a rolling test based on an analysis of the data from surrogate SNF-loaded sea transportation tests. Unfortunately, during the sea transportation tests, excessive rolling motion occurred on the ship during the test, causing the assemblies to slip and collide with the canister. Hence, we designed and conducted a separate test to simulate rolling in sea transportation to determine whether such impact loads can occur under normal conditions of SNF transport, with the test conditions for the fuel assembly to slide within the basket experimentally determined. Rolling tests were conducted while varying the rolling angle and frequency to determine the angles and frequencies at which the assemblies experienced slippage. The test results show that slippage of SNF assemblies can occur at angles of approximately 14° or greater because of rolling motion, which can generate impact loads. However, this result exceeds the conditions under which a vessel can depart for coastal navigation, thus deviating from the normal conditions required for SNF transport. Consequently, it is not necessary to consider such loads when evaluating the integrity of SNFs under normal transportation conditions.

저온 평판형 고체산화물 연료전지 내부 열 및 물질전달 현상에 대한 전산해석 (Computational Analysis of Heat and Mass Transfer in a Planar-type Solid Oxide Fuel Cell)

  • 정희석;차훈;손정락;노승탁
    • 한국신재생에너지학회:학술대회논문집
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    • 한국신재생에너지학회 2005년도 제17회 워크샵 및 추계학술대회
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    • pp.648-654
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    • 2005
  • The performance prediction of a planar-type solid oxide fuel ceil is conducted by a computational analysis. The transport processes are formulated with the help of a simplified treatment of heat generation by the electrochemical reaction. From the result of the computational analysis, it is shown that the electrochemical reaction is closely related to the transport phenomena inside a solid oxide fuel cell. Transport phenomena including heat and mass transfer have influence on the distribution of local current density and as a result, on the performance characteristics of the fuel cell. Computational analysis is also extended to the parametric study to investigate the performance behavior of the fuel cell with different amount of supplied fuel flow rates. It is also demonstrated that the mathematical formulation and computational procedures proposed in this study can be applied to prove the importance of the specific TPB(Three-Phase-Boundary) area in the manufacturing process of electrodes in a solid oxide fuel cell.

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