• 제목/요약/키워드: fuel burn-up

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SOFC/가스터빈 혼합발전을 위한 SOFC 생성물의 연소특성 (Combustion Characteristics of the SOFC Products for SOFC/Gas Turbine Hybrid Power Generation System)

  • 이병준;배철한
    • 한국연소학회지
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    • 제19권3호
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    • pp.44-52
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    • 2014
  • Solid oxide fuel cell(SOFC) makes electric power using hydrogen or reformed from methane and emits high temperature products that contain flammable species like hydrogen, carbon monoxide and methane which varies with operation condition. SOFC/gas turbine integrated system which uses thermal and chemical energy of the discharges is more efficient than SOFC itself. Burning character of the SOFC products will affect the efficiency and stability of the system. Experiments were conducted to know the characteristics of the flame for two typical composition of SOFC products, i.e. start-up and steady state composition. When coflowing air temperature was higher than $600^{\circ}C$, auto-ignitin occurred for both fuels. Though start-up fuel has higher contents of hydrogen, it makes longer flame than steady state composition. It was inferred that the amount of oxidizer necessary to burn makes this phenomenon. Steady state composition fuel was unstable since it contains lots of water. Nozzle that had 6 holes, distance between each hole was 16.7 times of hole diameter, improved the stability of the flame.

사용후핵연료의 연소도 변화에 따른 산화 및 OREOX 공정에서 핵분열기체 방출 특성 (Release Characteristics of Fission Gases with Spent Fuel Burn-up during the Voloxidation and OREOX Processes)

  • 박근일;조광훈;이정원;박장진;양명승;송기찬
    • 방사성폐기물학회지
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    • 제5권1호
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    • pp.39-52
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    • 2007
  • 사용후핵연료의 건식 재가공을 위한 핵연료 원격 제조공정중 분말제조를 위한 산화 및 OREOX(산화 환원공정)열처리 공정으로부터 $^{85}Kr$$^{14}C$ 핵분열기체의 방출거동을 정량적으로 평가하였다. 특히 사용후핵연료의 평균 연소도가 $27,000{\sim}65,000\;MWd/tU$ 범위내에서 연소도 변화에 따른 핵분열기체의 방출 분율은 측정한 실험결과와 ORIGEN 코드로부터 계산된 초기 inventory를 상호 비교하여 구하였다. $500^{\circ}C$ 1차 산화공정(voloxidation)에서 $^{85}Kr$$^{14}C(^{14}CO_2)$의 시간에 따른 방출거동은 $UO_2$ 핵연료의 $U_3O_8$으로의 분말화 정도와 밀접한 관련이 있는 것으로 보이며, 입계(grain-boundary)에 분포된 핵분열기체가 대부분 방출되는 것으로 여겨진다. 산화분말을 이용한 OREOX 공정으로부터 핵분열기체의 높은 방출율은 $700^{\circ}C$의 환원공정에서 온도 증가에 의한 기체 확산 및 $UO_2$으로의 환원에 의한 U 원자 이동성 증가에 의존하며 주로 inter-grain 및 intra-grain에 분포된 핵분열기체가 방출된 것으로 판단된다. 일차 산화공정시 $^{85}Kr$$^{14}C$ 핵분열기체의 방출 분율은 핵 연료 연소도가 증가함에 따라 높게 나타났고 방출 분율 범위는 총 inventory의 $6{\sim}12%$정도며, 산화분말의 OREOX 공정처리시 잔류 핵분열기체 대부분이 방출되는 것으로 보인다. 아울러 사용후핵 연료로부터 핵분열기체의 제거를 위해서는 고온 환원분위기보다는 산화에 의한 분말화가 더 효과적인 것으로 여겨진다.

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DME를 사용한 단기통 엔진의 연소특성에 관한 수치해석적 연구 (A Numerical Study on Combustion Characteristics of Single Cylinder Engine Fueled with DME)

  • 김현철;강우;나병철;김명환
    • 한국자동차공학회논문집
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    • 제14권4호
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    • pp.39-48
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    • 2006
  • In this research, in order to study the spray, combustion, and emission characteristics of the common rail DME engine, the target engine was disassembled, and 3D CAD file was constructed using a 3D measurement machine and a rapid prototyping machine. Using the obtained 3D geometry, fine moving meshes are generated, and three dimensional non-steady turbulence flow field and combustion phenomenon including spray were numerically analyzed. As a result, IMEP of DME and diesel in medium and high speed revolution showed similar performance. As the DME fuel start to burn in spray area, the vaporized fuel rapidly spreads squish area in low speed revolution. In the case of DME engine, CO and NOx are relatively consistent with experiment results. It was found that the break-up, evaporation, collision model of DME fuel need to be properly adjusted through matching the characteristics of fuel and injector for further improvement.

LPG엔진에서 수소연료 보조분사에 의한 희박연소특성 연구 (Lean Combustion Characteristics with Hydrogen Addition in a LPG Fuelled Spark Ignition Engine)

  • 오승묵;김창업;강건용
    • 한국자동차공학회논문집
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    • 제14권2호
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    • pp.114-120
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    • 2006
  • The basic effects of hydrogen addition for engine performance and emission were investigated in single cylinder research engine. Seven commercial injectors were tested to choose a suitable injector for hydrogen injection prior to its engine implementation. The hydrogen fuel leakage and flow rate were evaluated for each injector and KN3-1(Keihin, CO.) showed the best performance for hydrogen fuel. At the higher excess air ratio(${\lambda}=1.7$, 2.0), the better combustion stability was found with hydrogen addition even though its effect was small at lower excess air ratio (${\lambda}=1.0$, 1.3). Stable operation of the engine was even guaranteed at ${\lambda}=2.0$, if the amount of hydrogen gas was near 15% of total energy. In the lean region, ${\lambda}>1.3$, thermal efficiency was improved slightly while it was not clearly observed at ${\lambda}=1.0$, 1.3. It is considered that, in some cases, high temperature environment due to hydrogen combustion caused further heat loss to surroundings. Except for ${\lambda}=1.0$, with larger amount of hydrogen addition, CO was reduced drastically but it was emitted more at the leaner region. Nitric oxides(NOx) was increased a little more with hydrogen addition at ${\lambda}=1.0$, 1.3. However, at ${\lambda}>1.3$ its relative amount of emission was low. In addition, the amount of NOx was continuously decreased with hydrogen addition, but, at ${\lambda}=2.0$ the amount of NOx was lowered to 1/100 of that of ${\lambda}=1.0$. THC emission was significantly increased as air/fuel ratio was raised to leaner region due to misfire and partial burn.

Searching for the viability of using thorium-based accident-tolerant fuel for VVER-1200

  • Mohamed Y.M. Mohsen;Mohamed A.E. Abdel-Rahman;Ahmed Omar;Nassar Alnassar;A. Abdelghafar Galahom
    • Nuclear Engineering and Technology
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    • 제56권1호
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    • pp.167-179
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    • 2024
  • This study explores the feasibility of employing (U, Th)-based accident tolerant fuels (ATFs), specifically (0.8UO2, 0.2ThO2), (0.8UN, 0.2ThN), and (0.8UC, 0.2ThC). The investigation assesses the overall performance of these proposed fuel materials in comparison to the conventional UO2, focusing on deep neutronic and thermal-hydraulic (Th) analyses. Neutronic analysis utilized the MCNPX code, while COMSOL Multiphysics was employed for thermal-hydraulic analysis. The primary objective of this research is to overcome the limitations associated with traditional UO2 fuel by exploring alternative fuel materials that offer advantages in terms of abundance and potential improvements in performance and safety. Given the limited abundance of UO2, long-term sustainable nuclear energy production faces challenges. From a neutronic standpoint, the U-Th based fuels demonstrated remarkable fuel cycle lengths, except (0.8UN, 0.2ThN), which exhibited the minimum fuel cycle length and, consequently, the lowest fuel burn-up. Regarding thermal-hydraulic performance, (0.8UN, 0.2ThN) exhibited outstanding performance with significant margins against fuel melting compared to the other materials. Overall, when considering the integrated performance, the most favourable results were obtained with the use of the (0.8UC, 0.2ThC) fuel configurations. This study contributes valuable insights into the potential benefits of (U, Th)-based ATFs as a promising avenue for enhanced nuclear fuel performance.

디젤분무의 분열길이 측정에 관한 연구 (A Study on the Measurement of Break-up Length for the Diesel Sprays)

  • 장세호;라진홍
    • 동력기계공학회지
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    • 제3권3호
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    • pp.22-28
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    • 1999
  • The injected liquid does not break-up instantly after injection for diesel engine. There is some unbroken portion, which is the liquid core(The length of liquid core is called the break-up length) in the spray. If the liquid core is longer than the depth of the bowl in the small DI diesel engine, the liquid core impinges on the surface of the piston. Once the liquid core impinges on the surface, it cannot ignite or burn rapidly and thus prolongs burning time with a degradation in thermal efficiency. The break-up length of a diesel spray in a compressure vessel was measured by an electric resistance method, A voltage was applied between the nozzle and screen, bar, needle electrode inserted at various axial and radial positions into atomizing sprays. As a result, a current flows not only in the region of liquid core but also through the droplets of the spray. It is found that the break-up length measured with screen electrode is overestimated. The break-up length of the spray is found to be proportional to the square root of the density ratio of fuel and surrounding gas. The break-up length of the spray decreases as the injection pressure and the back pressure increase.

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AN EXPLORATORY STUDY OF THE EMISSION REDUCTION TECHNOLOGIES COMPLIANT WITH SULEV REGULATIONS

  • Kim, In Tak;Lee, Woo Jik;Yoon, Jong Seok;Park, Chung Kook
    • International Journal of Automotive Technology
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    • 제2권2호
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    • pp.63-75
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    • 2001
  • This paper describes the development of THC reduction technologies compliant with SULEV regulations. Technologies embodied by the developmental work include improvement of fuel spray atomization, quick warm-up through coolant control shut of, and acceleration of fuel atomization for the fast rise of cylinder head temp inside the water jacket as well as the improvement of combustion state. The technologies likewise entail reduced HC while operating in lean A/F condition during engine warm-up with the cold lean burn technology, individual cylinder A/F control for improvement of catalytic converting efficiency, after-treatment such as thin-wall catalyst, HC-adsorber and EHC and etc, through vehicle application evaluation in cold start. We carried out an experimental as well as a practical study against SULEV regulations, and the feasibility of adopting these items in vehicle was likewise investigated.

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국내 PWR 사용후핵연료에서 세슘, 스트론튬과 요오드의 갭 및 입계 재고량 측정 (Measurement of the Gap and Grain Boundary Inventories of Cs, Sr in and I in Domestic Used PWR Fuels)

  • 김승수;강광철;최종원;서항석;권수한;조원진
    • 방사성폐기물학회지
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    • 제5권1호
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    • pp.79-84
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    • 2007
  • 처분장에서 지하수로 쉽게 유출될 수 있는 방사성 핵종들의 양을 예측하기 위하여 국내 PWR 사용후핵연료 팰렛들의 갭(gap) 및 입계에 있는 용해성 원소들의 재고량을 측정하였다. 연소도가 $45{\sim}66$ GWD/MTU를 갖는 연료봉에서 얻은 펠렛들에서 세슘의 갭 재고량이 $0.85{\sim}1.7%$M로 나타났으며, 이는 핵분열 생성기체 유출률의 $1/6{\sim}1/3$에 해당하였다. 그러나 핵분열 생성기체 유출 률이 1%이하인 연료봉에서 취한 40 GWD/MTU이하의 연소도를 갖는 펠렛들의 경우, 세슘의 갭 재고량들을 핵분열 생성기체 유출률과 연관시키기는 곤란하였다. 갭 및 입계내 스트론튬의 재고량은 동일 연료봉내 펠렛에서는 크게 다르지 않았으며, 요오드의 갭 재고량은 핵분열 생성기체 유출률보다 작거나 유사한 값을 갖는 것으로 평가되었다.

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Transmutation Characteristics of Transuranics in a Transmutation Reactor Based on Low Aspect Ratio Toka

  • Hong, B.G.
    • 한국진공학회:학술대회논문집
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    • 한국진공학회 2014년도 제46회 동계 정기학술대회 초록집
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    • pp.456.1-456.1
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    • 2014
  • Transmutation characteristics of transuranics (TRU) in a transmutation reactor based on LAR (Low Aspect Ratio) tokamak as a neutron source are investigated. Optimum radial build of a transmutation reactor is found by coupled analysis of the tokamak systems and the neutron transport. The dependence of the transmutation characteristics on an aspect ratio, A in the range of 1.5 to 2.5, and on a fusion power in the range of 150 MW to 500 MW are investigated. Equilibrium fuel cycle is developed for effective transmutation and it is shown that with one unit of the transmutation reactor based on the LAR tokamak producing fusion power in the range of a few hundred MW, up to 3 PWRs (1.0 GWe capacity) can be supported with the burn-up fraction bigger than 50%.

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IRRADIATION DEVICE FOR IRRADIATION TESTING OF COATED PARTICLE FUEL AT HANARO

  • Kim, Bong Goo;Park, Sung Jae;Hong, Sung Taek;Lee, Byung Chul;Jeong, Kyung-Chai;Kim, Yeon-Ku;Kim, Woong Ki;Lee, Young Woo;Cho, Moon Sung;Kim, Yong Wan
    • Nuclear Engineering and Technology
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    • 제45권7호
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    • pp.941-950
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    • 2013
  • The Korean Nuclear-Hydrogen Technology Development (NHTD) Plan will be performing irradiation testing of coated particle fuel at HANARO to support the development of VHTR in Korea. This testing will be carried out to demonstrate and qualify TRISO-coated particle fuel for use in VHTR. The testing will be irradiated in an inert gas atmosphere without on-line temperature monitoring and control combined with on-line fission product monitoring of the sweep gas. The irradiation device contains two test rods, one has nine fuel compacts and the other five compacts and eight graphite specimens. Each compact contains about 260 TRISO-coated particles. The irradiation device is being loaded and irradiated into the OR5 hole of the in HANARO core from August 2013. The device will be operated for about 150 effective full-power days at a peak temperature of about $1030^{\circ}C$ in BOC (Beginning of Cycle) during irradiation testing. After a peak burn-up of about 4 atomic percentage and a peak fast neutron fluence of about $1.7{\times}10^{21}\;n/cm^2$, PIE (Post-Irradiation Examination) of the irradiated coated particle fuel will be performed at IMEF (Irradiated Material Examination Facility). This paper reviews the design of test rod and irradiation device for coated particle fuel, and discusses the technical results for irradiation testing at HANARO.