• 제목/요약/키워드: irradiated fuel

검색결과 155건 처리시간 0.023초

Microstructural Characteristics of the Fuel Cladding Tubes Irradiated in Kori Unit 1

초음파 조사 디젤유 적용 커먼레일 디젤기관 특성에 관한 연구 (Study on the Characteristics of Common-rail Diesel Engine with Ultrasoniccally Irradiated Diesel Fuel)

  • 임석연;정영철;조성철;류정인
    • 한국분무공학회지
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    • 제11권2호
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    • pp.69-74
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    • 2006
  • This is an experimental study on the performance characteristics and combustion characteristics of common-rail type diesel engine by using ultrasonic energy. It is carried out engine performance by engine dynamometer test and combustion characteristics using ultrasonically irradiated diesel fuel in comparison with using conventional diesel fuel. In analyzing the experiments of these results generally, these are obtained as follows. There is an affirmative effect on the side of the improvement of power and the reduction of smoke by applying the ultrasonically irradiated diesel fuel to the common rail engine. But there is less effect on the side of improvement of BSFC.

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커먼레일 디젤기관에 초음파 조사 바이오디젤유 적용 특성에 관한 연구 (A Study on the Application Characteristics of Ultrasonically Irradiated Bio-Diesel Fuel in Common-mil Direct Injection Diesel Engine)

  • 최두석;정영철;임석연;류정인
    • 한국자동차공학회논문집
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    • 제14권1호
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    • pp.109-114
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    • 2006
  • The reformed bio-diesel fuel irradiated by the ultrasonic wave is applied to the diesel engine of common rail in common use recently. This study has the object to examine the properties of engine performance and discharged materials. The bio-diesel fuel is mixed and used with the diesel fuel in common use at the ratio of $20\%\;or\; 100\%$. The ultrasonic energy is irradiated to the individually mixed fuel in order to reform the fuel. This fuel is applied to the engine in this experiment. And It is compared and analyzed from the experimental results with two cases irradiating the ultrasonic wave and no irradiating.

COMPARATIVE ANALYSIS OF STRUCTURAL CHANGES IN U-MO DISPERSED FUEL OF FULL-SIZE FUEL ELEMENTS AND MINI-RODS IRRADIATED IN THE MIR REACTOR

  • Izhutov, Aleksey.L.;Iakovlev, Valeriy.V.;Novoselov, Andrey.E.;Starkov, Vladimir.A.;Sheldyakov, Aleksey.A.;Shishin, Valeriy.Yu.;Kosenkov, Vladimir.M.;Vatulin, Aleksandr.V.;Dobrikova, Irina.V.;Suprun, Vladimir.B.;Kulakov, Gennadiy.V.
    • Nuclear Engineering and Technology
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    • 제45권7호
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    • pp.859-870
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    • 2013
  • The paper summarizes the irradiation test and post-irradiation examination (PIE) data for the U-Mo low-enriched fuel that was irradiated in the MIR reactor under the RERTR Program. The PIE data were analyzed for both full-size fuel rods and mini-rods with atomized powder dispersed in Al matrix as well as with additions of 2%, 5% and 13% of silicon in the matrix and ZrN protective coating on the fuel particles. The full-size fuel rods were irradiated up to an average burnup of ${\sim}60%^{235}U$; the mini-rods were irradiated to an average burnup of ${\sim}85%^{235}U$. The presented data show a significant increase of the void fraction in the U-Mo alloy as the U-235 burnup rises from ~ 40% up to ~ 85%. The effect of irradiation test conditions and U-235 burnup were analyzed with regard to the formation of an interaction layer between the matrix and fuel particles as well as generation of porosity in the U-Mo alloy. Shown here are changes in distribution of U fission products as the U-235 burnup increases from ~ 40% up to ~ 85%.

A Study on Reusable Metal Component as Burnable Absorber Through Monte Carlo Depletion Analysis

  • Muth, Boravy;Alrawash, Saed;Park, Chang Je;Kim, Jong Sung
    • 방사성폐기물학회지
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    • 제18권4호
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    • pp.481-496
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    • 2020
  • After nuclear power plants are permanently shut down and decommissioned, the remaining irradiated metal components such as stainless steel, carbon steel, and Inconel can be used as neutron absorber. This study investigates the possibility of reusing these metal components as neutron absorber materials, that is burnable poison. The absorption cross section of the irradiated metals did not lose their chemical properties and performance even if they were irradiated over 40-50 years in the NPPs. To examine the absorption capability of the waste metals, the lattice calculations of WH 17×17 fuel assembly were analyzed. From the results, Inconel-718 significantly hold-down fuel assembly excess reactivity compared to stainless steel 304 and carbon steel because Inconel-718 contains a small amount of boron nuclide. From the results, a 20wt% impurity of boron in irradiated Inconel-718 enhances the excess reactivity suppression. The application of irradiated Inconel-718 as a burnable absorber for SMR core was investigated. The irradiated Inconel-718 impurity with 20wt% of boron content can maintain and suppress the whole core reactivity. We emphasize that the irradiated metal components can be used as burnable absorber materials to control the reactivity of commercial reactor power and small modular reactors.

ANALYSIS OF HIGH BURNUP PRESSURIZED WATER REACTOR FUEL USING URANIUM, PLUTONIUM, NEODYMIUM, AND CESIUM ISOTOPE CORRELATIONS WITH BURNUP

  • KIM, JUNG SUK;JEON, YOUNG SHIN;PARK, SOON DAL;HA, YEONG-KEONG;SONG, KYUSEOK
    • Nuclear Engineering and Technology
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    • 제47권7호
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    • pp.924-933
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    • 2015
  • The correlation of the isotopic composition of uranium, plutonium, neodymium, and cesium with the burnup for high burnup pressurized water reactor fuels irradiated in nuclear power reactors has been experimentally investigated. The total burnup was determined by Nd-148 and the fractional $^{235}U$ burnup was determined by U and Pu mass spectrometric methods. The isotopic compositions of U, Pu, Nd, and Cs after their separation from the irradiated fuel samples were measured using thermal ionization mass spectrometry. The contents of these elements in the irradiated fuel were determined through an isotope dilution mass spectrometric method using $^{233}U$, $^{242}Pu$, $^{150}Nd$, and $^{133}Cs$ as spikes. The activity ratios of Cs isotopes in the fuel samples were determined using gamma-ray spectrometry. The content of each element and its isotopic compositions in the irradiated fuel were expressed by their correlation with the total and fractional burnup, burnup parameters, and the isotopic compositions of different elements. The results obtained from the experimental methods were compared with those calculated using the ORIGEN-S code.

Experimental and theoretical justification of passive heat removal system for irradiated fuel assemblies of the nuclear research reactor in a spent fuel pool

  • Ta Van Thuong;O.L. Tashlykov;S.M. Glukhov;D.E. Shumkov;Yu.V. Volchikhina
    • Nuclear Engineering and Technology
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    • 제55권6호
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    • pp.2088-2095
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    • 2023
  • The safety of nuclear installations is largely determined by the tightness of fuel elements cladding. As the Fukushima nuclear accident showed, the main task in case of loss of power supply is to ensure reliable removal of residual heat release from spent fuel pool (SFP) with irradiated fuel assemblies (IFAs). The paper presents the results of calculated-experimental studies and thermal-hydraulic modeling of temperature storage modes of IFAs in SFP. Experimental studies of SFP's temperature regime and calculated evaluation of residual heat removal due to the thermal conductivity of building structures surrounding the SFP were performed. To ensure the safe operation of research reactors, it's necessary to know the IFA's residual heat power (RHP) in the reactor and SFP, which is determined depending on the operating time of fuel assemblies (FAs) and the IFAs calculated holding time. The FAs operating time depends on the reactor energy output. The IFAs calculated holding time is determined by the fuel burnup, U-235 mass in the fuel, and reactor utilization factor. The IFAs fuel burnup was calculated using the MCU-PTR program. Also presented are the RHP's calculation results using some of the empirical dependencies. The concept of a passive heat removal system (PHRS) based on thermosyphon's operating principle was proposed.

Analysis of the Irradiated Nuclear Fuel Using the Heavy Atom and Neodynium Isotope Correlations with Burnup

  • Kim, Jung-Suk
    • Nuclear Engineering and Technology
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    • 제29권4호
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    • pp.327-335
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    • 1997
  • The correlation of isotope composition of uranium, plutonium and neodymium with the burnup in M uranium dioxide fuel has been investigated experimentally. The total and fractional($^{235}$ U) burnup were determined by Nd-148 and, U and Pu mass spectrometric method respectively. The isotope compositions of these elements, after their separation from the fuel samples were measured by mass spectrometric. The content of the elements in the irradiated fuel ore determined by isotope dilution mass spectrometric method using $^{233}$ U, $^{242}$ Pu and $^{150}$ Nd as spikes. The content of plutonium in the irradiated fuel was expressed by the correlation with uranium isotopes. The correlations between isotope compositions themselves and the total and fractional burnup ore compared with those calculated from ORIGEN2 code.

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CRDI 방식 디젤기관의 초음파 조사 Bio-diesel 혼합연료 적용 특성에 관한 실험 연구 (Experimental Study on the Application Characteristics of Bio-diesel blended Fuel by Ultrasonic Irradiation in CRDI type Diesel Engine)

  • 정영철;임석연;박성영;최두석;류정인
    • 한국분무공학회지
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    • 제12권3호
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    • pp.131-137
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    • 2007
  • This is an experimental study on characteristics of engine performance and discharged materials in common-rail type diesel engine. The bio-diesel fuel is mixed with the diesel fuel in common use at the ratio of 20% or 100%. The diesel fuel and blended fuel is irradiated by ultrasonic wave energy. The diese1 fuel, blended fuel, reformed diesel fuel and reformed blended fuel by ultrasonic wave energy are applied to the experimental engine individually. The results are compared with one of the diesel fuel in common use and analyzed.

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MECHANICAL AND IRRADIATION PROPERTIES OF ZIRCONIUM ALLOYS IRRADIATED IN HANARO

  • Kwon, Oh-Hyun;Eom, Kyong-Bo;Kim, Jae-Ik;Suh, Jung-Min;Jeon, Kyeong-Lak
    • Nuclear Engineering and Technology
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    • 제43권1호
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    • pp.19-24
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    • 2011
  • These experimental studies are carried out to build a database for analyzing fuel performance in nuclear power plants. In particular, this study focuses on the mechanical and irradiation properties of three kinds of zirconium alloy (Alloy A, Alloy B and Alloy C) irradiated in the HANARO (High-flux Advanced Neutron Application Reactor), one of the leading multipurpose research reactors in the world. Yield strength and ultimate tensile strength were measured to determine the mechanical properties before and after irradiation, while irradiation growth was measured for the irradiation properties. The samples for irradiation testing are classified by texture. For the irradiation condition, all samples were wrapped into the capsule (07M-13N) and irradiated in the HANARO for about 100 days (E > 1.0 MeV, $1.1{\times}10^{21}\;n/cm^2$). These tests and results indicate that the mechanical properties of zirconium alloys are similar whether unirradiated or irradiated. Alloy B has shown the highest yield strength and tensile strength properties compared to other alloys in irradiated condition. Even though each of the zirconium alloys has a different alloying content, this content does not seem to affect the mechanical properties under an unirradiated condition and low fluence. And all the alloys have shown the tendency to increase in yield strength and ultimate tensile strength. Transverse specimens of each of the zirconium alloys have a slightly lower irradiation growth tendency than longitudinal specimens. However, for clear analysis of texture effects, further testing under higher irradiation conditions is needed.