• Title/Summary/Keyword: Fuel Cycle

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Development of an Oxide Reduction Process for the Treatment of PWR Spent Fuel (PWR 사용후핵연료 처리를 위한 금속전환공정 개발)

  • Hur, Jin-Mok;Hong, Sun-Seok;Jeong, Sang-Mun;Lee, Han-Soo
    • Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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    • v.8 no.1
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    • pp.77-84
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    • 2010
  • Reduction of oxides has been investigated for the volume reduction and recycling of the spent oxide fuel from commercial nuclear power plants. Various oxide reduction methods were proposed and KAERI (Korea Atomic Energy Research Institute) is currently developing an electrochemical reduction process using a LiCl-$Li_2O$ molten salt as a reaction medium. The electrochemical reduction process, the front end of the pyroprocessing, can connect the PWR (Pressurized Water Reactor) oxide fuel cycle to a metal fuel cycle of the sodium cooled fast reactor. This paper summarizes KAERI efforts on the development, improvement, and scale-up of the oxide reduction process.

Utilization of the Stand-by Fuel Assemblies (예비 핵연료의 이용)

  • Kim, Hark-Rho;Chung, Chang-Hyun
    • Nuclear Engineering and Technology
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    • v.13 no.2
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    • pp.63-72
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    • 1981
  • The change in the design-basis refueling strategy caused by the unexpected nuclear fuel failures may result in discharging intact fuel assemblies which were irradiated in the positions symmetric to the failed ones in addition to the failed ones in order to maintain the symmetric power shape in the reactor core. In this work an attempt is made to reuse the intact fuel assemblies which were discharged before reaching the design turnup in the above-described situation so as to improve the fuel utilization. The TDCORE code is used to estimate the flux and power distribution, and the RELOAD-II code for searching the optimal loading pattern with the minimum assembly radial power peaking factor. For the case of the Ko-ri unit 1, its third cycle turnup could be extended to 11,648 MWD/MTU by reusing the four low-burned fuel assemblies removed at the end of the first cycle, and then the loading pattern is searched to the equilibrium cycle.

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THE STATUS AND PROSPECT OF DUPIC FUEL TECHNOLOGY

  • Yang Myung-Seung;Choi Hang-Bok;Jeong Chang-Joon;Song Kee-Chan;Lee Jung-Won;Park Geun-Il;Kim Ho-Dong;Ko Won-Il;Park Jang-Jin;Kim Ki-Ho;Lee Ho-Hee;Park Joo-Hwan
    • Nuclear Engineering and Technology
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    • v.38 no.4
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    • pp.359-374
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    • 2006
  • Since 1991, Korea, Canada and United States have performed the direct use of spent pressurized water reactor (PWR) fuel in the Canada deuterium uranium (CANDU) reactors (DUPIC) fuel development project. Unlike the Tandem fuel cycle, which requires a wet reprocessing, the DUPIC fuel technology can directly refabricate CANDU fuels from the PWR spent fuel and, therefore, is recognized as a highly proliferation-resistant fuel cycle technology, which can be adopted even in non-proliferation treaty countries. The Korea Atomic Energy Research Institute (KAERI) has fabricated DUPIC fuel elements in a laboratory-scale remote fuel fabrication facility. KAERI has demonstrated the fuel performance in the research reactor, and has confirmed the operational feasibility and safety of a CANDU reactor loaded with the DUPIC fuel using conventional design and analysis tools, which will be the foundation of the future practical and commercial uses of DUPIC fuel.

메탄올-물 혼합연료 기관에 관한 연구

  • 김응서;정진은
    • Journal of the korean Society of Automotive Engineers
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    • v.3 no.3
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    • pp.49-57
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    • 1981
  • A cycle simulation of 4 cycle spark ignition engine using methanol-water blend as a fuel has been developed for study of prediction of power, specific fuel consumption, mean effective pressure and thermal efficiency. One-dimensional flow model for intake process and thermodynamic model for combustion process were selected. After, performance test was made with conventional engine which was modified in consideration of fuel properties. And computational results by simulation have been compared with experimental results. As the agreement between computational and experimental results was good, prediction of engine performance by was possible.

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A Literature Review on Application of Signature Materials in Nuclear Forensics according to Domestic Nuclear Facilities and Fuel Cycle (국내 원자력시설 및 핵연료 주기에 따른 핵감식 표지물질 활용에 대한 고찰)

  • Jeon, Yeoryeong;Gwon, Da Yeong;Han, Jiyoung;Choi, Woo Cheol;Kim, Yongmin
    • Journal of the Korean Society of Radiology
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    • v.15 no.1
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    • pp.37-43
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    • 2021
  • Republic of Korea has many nuclear facilities in the country, and Democratic People's Republic of Korea(North Korea) locates in the surrounding country. Therefore, it is necessary to construct the target facility's nuclear forensic data in a preemptive response to the changing international situation. For this reason, this study suggests "signature" materials used to understand the origins and sources of nuclear and other radioactive materials, taking into account domestic nuclear facilities and the nuclear fuel cycle. In domestic, pressurized light water reactors and pressurized heavy water reactors are in operation, and enriched and natural uranium are used as fuels. In the front-end fuel cycle, the signature materials can be nature uranium and UF6 in the uranium enrichment process. The domestic back-end fuel cycle adopts a non-circulating cycle excluding the reprocessing process, and the primary signature material is spent nuclear fuel. According to IAEA recommendation, the importance of these materials as the signature and characteristic contents are suggested in this study. To prove the integrity of nuclear material and build a national nuclear forensics library, it is necessary to grasp the signature material and acquire the characteristic data considering the domestic nuclear facilities and the nuclear fuel cycle.

Technical Management Processes for Large National R&D Projects : Focused on Pyro Project (대형 국가 R&D 프로젝트의 기술관리 프로세스 : 파이로 프로젝트를 중심으로)

  • Kim, Jeong-Guk;Ko, Won-Il;Ku, Jeong-Hoe;Nam, Hyo-On
    • Journal of the Korean Society of Systems Engineering
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    • v.13 no.2
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    • pp.34-41
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    • 2017
  • The Pyro project, one of the large national R&D project to construct Korea Advanced Pyroprocessing Facility (KAPF), which has many goals such as development of pyro technology and process equipment, design of equipment and facility, construction, and test operation, is now under research and development. To reduce uncertainty and risk of such complex project, the technical management processes in systems engineering standards and NASA handbook were reviewed, and then the ten common technical management processes were selected for the large national R&D project to meet its goal successfully. And the essential technical management processes were finally suggested for Pyro project in consideration of current situation of the project.

Development of a Vehicle Driving Cycle in a Military Operational Area Based on the Driving Pattern (군 운용 지역에서 차량의 주행 패턴에 따른 주행모드 개발)

  • Choi, Nak-Won;Han, Dong-Sik;Cho, Seung-Wan;Cho, Sung-Lai;Yang, Jin-Saeng;Kim, Kwang-Suk;Chang, Young-June;Jeon, Chung-Hwan
    • Transactions of the Korean Society of Automotive Engineers
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    • v.20 no.4
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    • pp.60-67
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    • 2012
  • Most of a driving cycle is used to measure fuel consumption (FC) and emissions for a specified vehicle. A driving cycle was reflected geography and traffic characteristics for each country, also, driving pattern is affected these parameters such as vehicle dynamics, FC and emissions. Therefore, this study is an attempt to develop a driving cycle for military operational area. The proposed methodology the driving cycle using micro-trips extracted from real-world data. The methodology is that the driving cycle is constructed considering important parameters to be affected FC. Therefore, this approach is expected to be a better representation of heterogeneous traffic behavior. The driving cycle for the military operational area is constructed using the proposed methodology and is compared with real-world driving data. The running time and total distance of the final cycle is 1461 s, 13.10 km. The average velocity is 32.25 km/h and average grade is 0.43%. The Fuel economy in the final cycle is 5.93 km/l, as opposed to 6.10 km/l for real-world driving. There were about 3% differences in driving pattern between the final driving cycle and real-world driving.

A Study on the Reduction of HC Emissions by Fuel Injection Methods during the SI Engine Start (가솔린기관의 시동시 연료분사기법에 의한 HC 배출저감 연구)

  • Kim, Seong-Soo
    • 한국연소학회:학술대회논문집
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    • 2003.12a
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    • pp.257-262
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    • 2003
  • Engine-out HC emissions were investigated during engine start. The tests were conducted on a 1.5L, 4-cylinder, 16 valve, multipoint-port-fuel-injection gasoline engine at different coolant temperatures and fuel injection-skip methods; no skip, 1 cycle-skip and 3 cycle-skip. To understand the characteristics of engine-out HC emissions, HC concentration was measured at a exhaust port using a Fast Response Flame Ionization Detector (FRFID). The result show that HC emissions were emitted at the cold coolant temperature much higher than those of the hot coolant. In additions, the fuel injection skip highly reduced engine-out HC emissions. It is convinced that optimized fuel injection skips according to coolant temperatures could be applied to reduce HC emissions during SI engine start.

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Verification and Development of Simulation Model for Fuel Consumption Calculation between ICEV and PHEV (자동차 동력원별(ICEV, PHEV) 연비산출 모델개발 및 이의 검증)

  • Kim, J.W.;Park, J.M.;Kim, T.K.;Lee, J.W.
    • Journal of ILASS-Korea
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    • v.22 no.2
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    • pp.47-54
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    • 2017
  • $CO_2$ emission regulation will be prescribed and main issue in automotive industry. Mostly, vehicle's fuel efficiency deeply related to $CO_2$ emission is regulated by qualified driving test cycle by using chassis dynamometer and exhaust gas analyser. But, real driving fuel consumption rate depends so much on the individual usage profile and where it is being driven: city traffic, road conditions. In this study, vehicle model of fuel consumption rate for ICEV and PHEV was developed through co-simulation with CRUISE model and Simulink based on driving control model. The simulation results of fuel consumption rate were analysed with on-road vehicle data and compared with its official level.

Multilateral Nuclear Approaches (MNAs), Factors and Issues Lessons from IAEA Study to Regional Cooperation (다자간 원자력 협력: 요소와 현안)

  • Hwang Yong-Soo
    • Proceedings of the Korean Radioactive Waste Society Conference
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    • 2005.06a
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    • pp.56-66
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    • 2005
  • In response to the increasing emphasis being placed on the importance of international cooperation as part of global efforts to cope with growing non proliferation, and security, concerns in the nuclear field, the Director General of the International Atomic Energy Agency (IAEA), Mohamed ElBaradei, appointed an international group of experts to consider possible multilateral approaches to the nuclear fuel cycle. The mandate of the Expert Group was three fold: ${\bullet}$ To identify and provide an analysis of issues and options relevant to multilateral approaches to the front and back ends of the nuclear fuel cycle; ${\bullet}$ To provide an overview of the policy, legal, security, economic, institutional and technological incentives and disincentives for cooperation in multilateral arrangements for the front and back ends of the nuclear fuel cycle; and ${\bullet}$ To provide a brief review of the historical and current experiences and analyses relating to multilateral fuel cycle arrangements relevant to the work of the Expert Group. The overall purpose was to assess MNAs in the framework of a double objective: strengthening the international nuclear non proliferation regime and making the peaceful uses of nuclear energy more economical and attractive. The Group identifies options for MNAs - options in terms of policy, institutional and legal factors - for those parts of the nuclear fuel cycle of greatest sensitivity from the point of view of proliferation risk. It also reflects the Groups deliberations on the corresponding benefits and disadvantages (pros and cons) of the various options and approaches. Although the Expert Group was able to agree to forward the resulting report to the Director General, it is important to note that the report does not reflect agreement by all of the experts on any of the options, nor a consensus assessment of their respective value. It is intended only to present options for MNAs, and to reflect on the range of considerations which could impact on the desirability and feasibility of those options.

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