• Title/Summary/Keyword: Standard fuel

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A Study on Compatibility of Vehicle Using Alternative Fuels (자동차 대체연료의 상호호환성 연구)

  • Lee, Taek-Hee;Kang, Seung-Jin
    • The Transactions of the Korean Institute of Electrical Engineers P
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    • v.61 no.2
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    • pp.74-81
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    • 2012
  • The purpose of this study provides the theoretical model for protecting the economic and social loss from the current alternative fuel vehicle which is developed without compatibility and senseless one's own through verifying the statistical significant by method of measuring analysis. The market scale of alternative fuel vehicle depends on customer's and station's expectation about the number of potential vehicle users. It is very difficult for vehicle manufacturer to make a decision on the standard alternative fuel vehicle as it might reduce profit and market share. Accordingly, the development of alternative fuel vehicle should have manufacturer confident on the potential profit in the future. Moreover, if we decide to use the non-standard fuel after we started to use the standard fuel, it would take a huge cost comparing with starting to use the standard fuel only. As a result, once one of companies starts to provide the non-standard fuel service, it is getting more difficult to use the standard fuel going forward. Consequently, we may review the possibility of choice on the standard fuel before the vehicle manufacturer starts service with non-standard fuel.

FISSION PRODUCT RELEASE ASSESSMENT FOR A LARGE BREAK LOCA IN CANDU REACTOR LOADED WITH CANFLEX-NU FUEL BUNDLES

  • Oh, Dirk-Joo;Ohn, Myeong-Yong;Lee, Kang-Moon;Suk, Ho-Chun
    • Proceedings of the Korean Nuclear Society Conference
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    • 1997.05a
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    • pp.484-488
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    • 1997
  • Fission product release (FPR) assessment for 100% reactor outlet header (ROH) break in CANDU reactor loaded with CANFLEX-NU fuel bundles has been performed. The predicted results are compared with those for the reactor loaded with standard 37-element bundles. The fuel failure thresholds for the CANFLEX and standard bundle elements are very similar. All the sheaths at the corresponding fuel failure thresholds for the CANFLEX and standard bundles fail due to the significant cracks in the surface oxide, except those for the CANFLEX inner element at burnups of 220 to 240 MW.h/kg(U), which fail due to the excessive diametral strain. The fuel failure analysis predicts that the number of failed fuel elements for the CANFLEX bundle case is none, while that for the standard bundle case is 1827. The total (gap plus bound) I-131 releases for the CANFLEX and standard bundles are none and 5889 TBq, respectively The significant reduction of the number of failed fuel elements and FPR for the CABFKEX fuel bundle is attributed to the lower linear power of the CANFLEX fuel bundle compared with the standard fuel bundle.

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FUEL CHANNEL ANALYSIS FOR 35% RIH BREAK IN CANDU REACTOR LOADED WITH CANFLEX-RU FUEL BUNDLES

  • Oh, Dirk-Joo;Lee, Young-Ouk;Jeong, Chang-Joon;Lim, Hong-Sik;Suk, Ho-Chun
    • Proceedings of the Korean Nuclear Society Conference
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    • 1998.05a
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    • pp.719-724
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    • 1998
  • A preliminary fuel channel analysis for 35% reactor inlet header (RIH) break in CANDU reactor loaded with the CANFLEX-RU fuel bundles has been performed. The predicted results are compared with those for the reactor compared with those for the reactor loaded with standard 37-element bundles. The maximum fuel centerline and sheath temperatures for the CANFLEX-RU bundle channel were lower by 338 and 122 $^{\circ}C$, respectively, than those for the standard bundle because of the Bower maximum linear power of the CANFLEX-RU bundle In spite of the 0.4 FPS higher power pulse of the CANFLEX-RU bundle case. Fuel integrity margin to fuel breakup for the CANFLEX-RU bundle is about 50 J/g higher than that for the standard bundle. The PT/CT contact for the CANFLEX-RU bundle occurred 2 s later than that for the standard bundle. The PT/CT contact temperature for the CANFLEX-RU bundle was 2 $^{\circ}C$ lower than that for the standard bundle. These provide the CANFLEX-RU bundle with the negligibly enhanced safety margin for the fuel channel integrity in CANDU 6 reactor, compared with the standard bundle.

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Enthalpy and Void Distributions in Subchannels of PHWR Fuel Bundles

  • Park, J.W.;Choi, H.;Rhee, B.W.
    • Proceedings of the Korean Nuclear Society Conference
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    • 1998.05a
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    • pp.502-507
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    • 1998
  • Two different types the CANDU fuel bundles hue been modeled for the ASSERT-IV code subchannel analysis. From calculated values of mixture enthalpy and void paction distributions in the fuel bundles, it is found that net buoyancy effect is pronounced in the central region of the DUPIC fuel bundle when compared with the standard CANDU fuel bundle. It is also found that the central region of the DUPIC fuel bundle can be cooled more efficiently than that of the standard fuel bundle. From calculated mixture enthalpy distribution at the exit of fuel channel, it is found that the mixture enthalpy and void fraction can be highest in the peripheral region of the DUPIC fuel bundle. On the other hand, the enthalpy and the void fraction were found to be highest in the central region of the standard CANDU fuel bundle at the exit of the fuel channel. This study shows that the subchannel analysis is very useful assessing thermal behavior of the fuel bundle that could be used in CANDU reactors.

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THERMAL-HYDRAULIC CHARACTERISTICS FOR CANFLEX FUEL CHANNEL USING BURNABLE POISON IN CANDU REACTOR

  • BAE, JUN HO;JEONG, JONG YEOB
    • Nuclear Engineering and Technology
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    • v.47 no.5
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    • pp.559-566
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    • 2015
  • The thermalehydraulic characteristics for the CANadian Deuterium Uranium Flexible (CANFLEX)-burnable poison (BP) fuel channel, which is loaded with a BP at the center ring based on the CANFLEX-RU (recycled uranium) fuel channel, are evaluated and compared with that of standard 37-element and CANFLEX-NU (natural uranium) fuel channels. The distributions of fuel temperature and critical channel power for the CANFLEX-BP fuel channel are calculated using the NUclear Heat Transport CIRcuit Thermohydraulics Analysis Code (NUCIRC) code for various creep rate and burnup. CANFLEX-BP fuel channel has been revealed to have a lower fuel temperature compared with that of a standard 37-element fuel channel, especially for high power channels. The critical channel power of CANFLEX-BP fuel channel has increased by about 10%, relative to that of a standard 37-element fuel channel for 380 channels in a core, and has higher value relative to that of the CANFLEX-NU fuel channel except the channels in the outer core. This study has shown that the use of a BP is feasible to enhance the thermal performance by the axial heat flux distribution, as well as the improvement of the reactor physical safety characteristics, and thus the reactor safety can be improved by the use of BP in a CANDU reactor.

Vibration Fatigue Analysis of Automotive Fuel Tank Using Transfer Function Method (Transfer Function Method를 이용한 자동차 연료탱크의 진동 피로 해석에 대한 연구)

  • Ahn, Sang Ho
    • Journal of Auto-vehicle Safety Association
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    • v.12 no.3
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    • pp.27-33
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    • 2020
  • In this paper, the process of predicting efficient durability performance for vibration durability test of automobile parts using vibration test load on automobile fuel tank is presented. First of all, the common standard load that can be applied to the initial development process of the automobile was used for the fuel tank and the vulnerability of the fuel tank to the vibration fatigue load was identified through frequency response analysis. In addition, the vulnerability of the fuel tank was re-enacted through vibration durability test results, and the scale factor was applied to the standard load. In order to predict the vibration durability performance required for detailed design, vibration fatigue analysis was performed on the developed vehicle with the frequency of vibration severity equivalent to the durability test, and the vulnerability and life span of the fuel tank were identified through the process of applying weights to these selected standard loads, thereby reducing the test time of the development vehicle.

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

  • Lim, Eui Soon;Kim, Jae-Kon;Jung, Choong-Sub
    • 한국신재생에너지학회:학술대회논문집
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    • 2011.11a
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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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A feasibility study on Introducing Reference Fuel(Diesel) for Testing Vehicles in South Korea (국내 차량 인증시험용 표준연료(경유) 도입 필요성 검토 연구)

  • Hwang, Inha;Kang, Hyungkyu;Seong, Sangrae;Song, Hoyoung;Ha, Jonghan;Na, Byungki
    • Journal of the Korean Applied Science and Technology
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    • v.34 no.4
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    • pp.974-985
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    • 2017
  • Although the number of registered cars in South Korea is about 22million but, there is no national standard for automobile reference fuel in South Korea. Reference fuel is the fuel used for certificating vehicle performance, emissions and fuel economy. Now, domestic market fuels are used as reference fuel. However, the quality of domestic market fuel is constantly changing by seasonal and fuel manufacturers. It may effect vehicle performance, emissions and fuel efficiency test result. On this study, market diesel fuel quality was monitored and reference fuel standard(draft) was set by reflecting market fuel monitoring result. Reference fuel standard(draft) was applied to CRDI engine.

International Standards trend on Hydrogen fuel quality (ISO/TC197/WG12의 수소품질 국제표준화 동향)

  • Cho, Sung-Kook;Cho, Chang-Ae;Lee, Taeck-Hong
    • 한국신재생에너지학회:학술대회논문집
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    • 2009.06a
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    • pp.739-743
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    • 2009
  • Japan is leading standards for the hydrogen fuel quality on the PEMFC(Proton Exchange Membrane Fuel Cell) vehicle at ISO/TC197/WG12. However, it has many problems to solve the standard of measurement and the test method. because the standard of measurement which was proposed in Japan is too high to reach the technique for many countries. it might not control standards for the hydrogen fuel quality on the PEMFC vehicle in Korea. So we need to develop the study of standards and the technique of measurement continuously for the International Standards Meeting.

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Analysis of Standard and FLIP Fuel Mixed Loading Patterns in TRIGA Mark-III Reactor

  • Kim, Jung-Do;Lee, Jong-Tai;Yook, Chong-Chul
    • Nuclear Engineering and Technology
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    • v.11 no.4
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    • pp.287-293
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    • 1979
  • Mixed standard-FLIP fuel loading patterns in the TRIGA Mark-III reactor were analyzed. It was judged that the mixed loading pattern with the standard fuel in the B-ring and the FLIP fuel in other rings was mostly desirable in view of fuel temperature, cooling condition with the natural convection, or effective thermal flux utilization in the central thimble. In addition, tile maximum useful flux in tile reactor beamports versus the loading patterns was evaluated.

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