• 제목/요약/키워드: Energy & fuel technology

검색결과 2,731건 처리시간 0.029초

Neutronic design and evaluation of the solid microencapsulated fuel in LWR

  • Deng, Qianliang;Li, Songyang;Wang, Dingqu;Liu, Zhihong;Xie, Fei;Zhao, Jing;Liang, Jingang;Jiang, Yueyuan
    • Nuclear Engineering and Technology
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    • 제54권8호
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    • pp.3095-3105
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    • 2022
  • Solid Microencapsulated Fuel (SMF) is a type of solid fuel rod design that disperses TRISO coated fuel particles directly into a kind of matrix. SMF is expected to provide improved performance because of the elimination of cladding tube and associated failure mechanisms. This study focused on the neutronics and some of the fuel cycle characteristics of SMF by using OpenMC. Two kinds of SMFs have been designed and evaluated - fuel particles dispersed into a silicon carbide matrix and fuel particles dispersed into a zirconium matrix. A 7×7 fuel assembly with increased rod diameter transformed from the standard NHR200-II 9×9 array was also introduced to increase the heavy metal inventory. A preliminary study of two kinds of burnable poisons (Erbia & Gadolinia) in two forms (BISO and QUADRISO particles) was also included. This study found that SMF requires about 12% enriched UN TRISO particles to match the cycle length of standard fuel when loaded in NHR200-II, which is about 7% for SMF with increased rod diameter. Feedback coefficients are less negative through the life of SMF than the reference. And it is estimated that the average center temperature of fuel kernel at fuel rod centerline is about 60 K below that of reference in this paper.

PROGRESS IN NUCLEAR FUEL TECHNOLOGY IN KOREA

  • Song, Kun-Woo;Jeon, Kyeong-Lak;Jang, Young-Ki;Park, Joo-Hwan;Koo, Yang-Hyun
    • Nuclear Engineering and Technology
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    • 제41권4호
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    • pp.493-520
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    • 2009
  • During the last four decades, 16 Pressurized Water Reactors (PWR) and 4 Pressurized Heavy Water Reactors (PHWR) have been constructed and operated in Korea, and nuclear fuel technology has been developed to a self-reliant state. At first, the PWR fuel design and manufacturing technology was acquired through international cooperation with a foreign partner. Then, the PWR fuel R&D by Korea Atomic Energy Research Institute (KAERI) has improved fuel technology to a self-reliant state in terms of fuel elements, which includes a new cladding material, a large-grained $UO_2$ pellet, a high performance spacer grid, a fuel rod performance code, and fuel assembly test facility. The MOX fuel performance analysis code was developed and validated using the in-reactor test data. MOX fuel test rods were fabricated and their irradiation test was completed by an international program. At the same time, the PWR fuel development by Korea Nuclear Fuel (KNF) has produced new fuel assemblies such as PLUS7 and ACE7. During this process, the design and test technology of fuel assemblies was developed to a self-reliant state. The PHWR fuel manufacturing technology was developed and manufacturing facility was set up by KAERI, independently from the foreign technology. Then, the advanced PHWR fuel, CANFLEX(CANDU Flexible Fuelling), was developed, and an irradiation test was completed in a PHWR. The development of the CANFLEX fuel included a new design of fuel rods and bundles.. The nuclear fuel technology in Korea has been steadily developed in many national R&D programs, and this advanced fuel technology is expected to contribute to a worldwide nuclear renaissance that can create solutions to global warming.

The relationship between public acceptance of nuclear power generation and spent nuclear fuel reuse: Implications for promotion of spent nuclear fuel reuse and public engagement

  • Roh, Seungkook;Kim, Dongwook
    • Nuclear Engineering and Technology
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    • 제54권6호
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    • pp.2062-2066
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    • 2022
  • Nuclear energy sources are indispensable in cost effectively achieving carbon neutral economy, where public opinion is critical to adoption as the consequences of nuclear accident can be catastrophic. In this context, discussion on spent nuclear fuel is a prerequisite to expanding nuclear energy, as it leads to the issue of radioactive waste disposal. Given the dearth of study on spent nuclear fuel public acceptance, we use text mining and big data analysis on the news article and public comments data on Naver news portal to identify the Korean public opinion on spent nuclear fuel. We identify that the Korean public is more interested in the nuclear energy policy than spent nuclear fuel itself and that the alternative energy sources affect the position towards spent nuclear fuel. We recommend relating spent nuclear fuel issue with nuclear energy policy and environmental issues of alternative energy sources to further promote spent nuclear fuel.

Development of Treatment Process for Residual Coal from Biosolubilization

  • Rifella, Archi;Shaur, Ahmad;Chun, Dong Hyuk;Kim, Sangdo;Rhim, Young Joon;Yoo, Jiho;Choi, Hokyung;Lim, Jeonghwan;Lee, Sihyun;Rhee, Youngwoo
    • 청정기술
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    • 제24권2호
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    • pp.119-126
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    • 2018
  • This study introduced a treatment process that was developed to treat Indonesian low-rank coal with high-ash content, which has the same characteristics as residual coal from the biosolubilization process. The treatment process includes separation of ash, solid-liquid separation, pelletizing, and drying. To reduce the ash content, flotation was performed using 4-methyl-2-pentanol (MIBC) as frother, and kerosene, waste oil, and cashew nut shell liquid (CNSL) as collectors. The increasing amount of collector had an effect on combustible coal recovery and ash reduction. After flotation, a filter press, extruder, and an oven drier were used to make a dried coal pellet. Then another coal pellet was made using asphalt as a binder. The compressive strength and friability of the coal pellets were tested and compared.

Experimental measurement of stiffness coefficient of high-temperature graphite pebble fuel elements in helium at high temperatures

  • Minghao Si;Nan Gui;Yanfei Sun;Xingtuan Yang;Jiyuan Tu;Shengyao Jiang
    • Nuclear Engineering and Technology
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    • 제56권5호
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    • pp.1679-1686
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    • 2024
  • Graphite material plays an important role in nuclear reactors especially the high-temperature gas-cooled reactors (HTGRs) by its outstanding comprehensive nuclear properties. The structural integrity of graphite pebble fuel elements is the first barrier to core safety under any circumstances. The correct knowledge of the stiffness coefficient of the graphite pebble fuel element inside the reactor's core is significant to ensure the valid design and inherent safety. In this research, a vertical extrusion device was set up to measure the stiffness coefficient of the graphite pebble fuel element by the Institute of Nuclear and New Energy Technology (INET) of Tsinghua University in China. The stiffness coefficient equations of graphite pebble fuel elements at different temperatures are given (in a helium atmosphere). The result first provides the data on the high-temperature stiffness coefficient of pebbles in helium gas. The result will be helpful for the engineering safety analysis of pebble-bed nuclear reactors.

Stress Analysis of pipe supports

  • Lee, H.H.;Lee, J.M.;Park, S.K.;Lee, C.Y.
    • 한국원자력학회:학술대회논문집
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    • 한국원자력학회 2005년도 추계학술발표회
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    • pp.701-702
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    • 2005
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국내 CNG 가스연료 자동차의 에너지소비효율 측정 및 계산절차에 관한 연구 (A Study on Energy Consumption Rate Measurement and Calculation Procedures of Domestric CNG Gaseous Fueled Vehicle)

  • 서영호;권석주;강은정
    • 융복합기술연구소 논문집
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    • 제3권2호
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    • pp.57-60
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    • 2013
  • The purpose of this study is to analysis of how to calculate fuel efficiency in major development countries (U.S. and Europe) and energy consumption formular derivation of domestic CNG fuel and prove by vehicle test. The formula of fuel consumption is different in mpg(mile per gallon), l/100km, and km/l each countries. CNG fuel has a significant impact on fuel density, composition, and Hydro-Carbon ratio. So, this study how to measurement and calculation procedures of CNG gaseous fueled vehicle energy consumption rate.

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방사선을 이용한 연료전지막 국내 제조 기술 개발 현황 (Current R&D Status of Fuel Cell Membranes by Radiation in Korea)

  • 신준화;손준용;노영창;강태진;김동수;임돈순;이병헌;김재호
    • 방사선산업학회지
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    • 제6권4호
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    • pp.289-297
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    • 2012
  • Since Nafion is very expensive and shows the decreased fuel cell performance over $80^{\circ}C$ operating temperature, much work has been carried out in the search for cheaper membrane with high fuel cell performance. Radiation is known to be very useful for the preparation of the polymer electrolyte membranes since it can be effectively used for the introduction of ion conducting functional groups into the commercial film with high mechanical and chemical properties. Here, we summarize the our recent progress in the development of fuel cell membranes by utilizing radiation.

발전용 바이오중유의 혼합비율에 따른 배출가스 특성 연구 (A Study on the Emission Characteristics for Blended Power Bio-Fuel Oil)

  • 하종한;전철환;권용재
    • 한국수소및신에너지학회논문집
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    • 제26권5호
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    • pp.484-492
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    • 2015
  • As our government is actively introducing the RPS (Renewable Portfolio Standards) as a national renewable energy obligation policy, power producers are using the various renewable energy to meet the RPS supply quota since 2012. Recently, it is appling to use power bio-fuel oil in bio-fuel oil demonstration project with power companies. In general, power bio-fuel oils are composed of mixture products of vegetable oil, animal fat, fatty acid ester and waste oil. It is already developing for a power plant as a renewable energy abroad. In Korea, it is studying a 100% combustion and blended combustion of heavy fuel oil and bio-fuel oil. In this study, we investigated fuel characteristics of mixed power bio-fuel oil and its emission performance. Especially, it was reduced emissions of bio-oil in industrial boilers due to bio-fuel properties as compare with fuel oil.