• Title/Summary/Keyword: reference energy

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The Daylight and Energy Performance Evaluation of Multi-purpose Solar Window System Using Simulaton Program (시뮬레이션에 의한 다기능 복합 솔라윈도우 시스템의 채광과 에너지성능평가)

  • Jeong, Yeol-Wha;Lee, Seun-Myung
    • Journal of the Korean Solar Energy Society
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    • v.31 no.6
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    • pp.103-110
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    • 2011
  • The aim of this study was to analysis the Heating/cooling performance and Daylighting performance of Solar Window System built in apartments. the solar window is the idea to integrate daylight as a third form of solar energy into a PV/Solar Collector system. The process of this study is as follows: 1)Solar Window system was designed through the investigation of previous paper and work. 2)The simulation program(Lightscape3.2) was used in daylighting performance analysis. the reference model of simulation was made up to analysis daylighting performance on Solar Window system. 3)The simulation program(ESP-r, Therm5.0, Window6.0) was used in energy performance analysis. the reference model of simulation was made up to analysis energy and daylighting performance on Solar Window system. 4)The Size of Simulation model for daylighting and heating/cooling energy analysis was $148.5m^2$ 5)The lighting performance analysis was carried out with various variants, such as the size and installed area of Solar Window system. 6)Energy performance simulation was carried out with various variants, such as Integrated U-value of Solar Window system according to its position, installed angle and insulation thickness. Consequently, When Solar Window system is equipped with balcony window of Apartment, Annual heating and cooling energy of reference model was cut down at the average of $4.1kWh/m^2$ or 4.2%.

Precise Determination of Silicon in Ceramic Reference Materials by Prompt Gamma Activation Analysis at JRR-3

  • Miura, Tsutomu;Matsue, Hideaki
    • Nuclear Engineering and Technology
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    • v.48 no.2
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    • pp.299-303
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    • 2016
  • Prompt gamma activation analysis using a thermal neutron-guided beam at Japan Atomic Energy Agency JRR-3M was applied for the precise determination of Si in silicon nitride ceramic reference materials [Japan Ceramic Reference Material (JCRM) R 003]. In this study, the standard addition method coupled with internal standard was used for the nondestructive determination of Si in the sample. Cadmium was used as internal standard to obtain the linear calibration curves and to compensate for the neutron beam variability. The analytical result of determining Si in JCRM R 003 silicon nitride fine powder ceramic reference materials using prompt gamma activation analysis was in good agreement with that obtained by classical gravimetric analysis. The relative expanded measurement uncertainty (k = 2) associated with the determined value was 2.4%.

Sequential determination of $^{239,240}Pu,\;^{238}Pu,\;^{90}Sr$ and $^{241}Am$ Isotopes in Environmental Samples

  • Lee, Myung-Ho;Jo, Mi-Hyun;Park, Jong-Ho;Ahn, Hong-Joo;Lee, Chang-Heon;Song, Kyu-Seok
    • Proceedings of the Korean Radioactive Waste Society Conference
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    • 2009.11a
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    • pp.407-408
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    • 2009
  • In this work, a quantitative method of the sequential separation of $^{90}Pu,\;^{90}Sr$ and $^{241}Am$ nuclides was developed in environmental soil samples using by an anion exchange resin connected with a Sr Spec resin. The sequential methods of Pu, $^{90}Sr$ and $^{241}Am$ nuclides can reduce analysis cost and time. With the sequential methodupdated in this study, the activity concentrations of $^{239,240}Pu,\;^{90}Sr$ and $^{241}Am$ in the IAEA reference materials were close to the reference values reported by the IAEA.

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Energy optimization of a Sulfur-Iodine thermochemical nuclear hydrogen production cycle

  • Juarez-Martinez, L.C.;Espinosa-Paredes, G.;Vazquez-Rodriguez, A.;Romero-Paredes, H.
    • Nuclear Engineering and Technology
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    • v.53 no.6
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    • pp.2066-2073
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    • 2021
  • The use of nuclear reactors is a large studied possible solution for thermochemical water splitting cycles. Nevertheless, there are several problems that have to be solved. One of them is to increase the efficiency of the cycles. Hence, in this paper, a thermal energy optimization of a Sulfur-Iodine nuclear hydrogen production cycle was performed by means a heuristic method with the aim of minimizing the energy targets of the heat exchanger network at different minimum temperature differences. With this method, four different heat exchanger networks are proposed. A reduction of the energy requirements for cooling ranges between 58.9-59.8% and 52.6-53.3% heating, compared to the reference design with no heat exchanger network. With this reduction, the thermal efficiency of the cycle increased in about 10% in average compared to the reference efficiency. This improves the use of thermal energy of the cycle.

Study of neutron energy and directional distribution at the Beloyarsk NPP selected workplaces

  • Pyshkina, Mariia;Vasilyev, Aleksey;Ekidin, Aleksey;Nazarov, Evgeniy;Nikitenko, Vitaly;Pudovkin, Anton
    • Nuclear Engineering and Technology
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    • v.53 no.5
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    • pp.1723-1729
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    • 2021
  • Energy and directional distribution of neutrons at the Beloyarsk NPP workplaces is a subject of this study. Measurements of H*(10) rate and neutron energy distribution were taken at 8 workplaces, which can be divided into three categories: work with spent or fresh nuclear fuel, work with radionuclide neutron sources, work at the rooms adjusted to reactors. The Hp(10) measurements were performed only at 6 out of 8 locations, due to the fact that long term placing of an effective neutron moderator in fresh nuclear fuel storage facility is forbidden. As a result of the research energy and direction distribution of the neutron fields at 8 locations of the Beloyarsk NPP workplaces was obtained. To estimate the accuracy of the H*(10) rate and Hp (10) measurements the reference values of dose equivalents were calculated using energy and directional distribution. To take into account the difference between the reference values and the measured results site-specific correction factors were calculated.

Effect of Reference Current and Depth of Cut on Electro-Discharge Energy in Electro-Discharge Truing Process for Metal-Bonded Grinding Wheel (금속결합제 연삭숫돌의 방전트루잉에서 기준전류와 절입깊이가 방전에너지에 미치는 영향)

  • Shin, Gun-Hwi;Kwak, Tae-Soo;Jung, Myung-Won;Kwak, Ihn-Sil
    • Journal of the Korean Society for Precision Engineering
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    • v.33 no.6
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    • pp.485-490
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    • 2016
  • This study focused on developing an electro-discharge truing method for the ELID grinding process using a metal-bonded grinding wheel. The truing process in grinding plays important roles in enhancing the quality of the ground surface. In this study, a reference current in the electro-discharge truing process was confirmed to be a viable solution for efficient truing through performance experiments. Current and voltage variation experiments were carried out and the variation output data were collected with a monitoring program to understand the electrodischarge phenomenon that occurs between metal-bonded grinding wheels and copper electrodes. The experimental results showed that as the reference current decreased, the average electro-discharge energy decreased. Therefore, the reference current can be used as an indicator to estimate the size of the gap between the truer and grinding wheel.

Calibration of digital wide-range neutron power measurement channel for open-pool type research reactor

  • Joo, Sungmoon;Lee, Jong Bok;Seo, Sang Mun
    • Nuclear Engineering and Technology
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    • v.50 no.1
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    • pp.203-210
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    • 2018
  • As the modernization of the nuclear instrumentation system progresses, research reactors have adopted digital wide-range neutron power measurement (DWRNPM) systems. These systems typically monitor the neutron flux across a range of over 10 decades. Because neutron detectors only measure the local neutron flux at their position, the local neutron flux must be converted to total reactor power through calibration, which involves mapping the local neutron flux level to a reference reactor power. Conventionally, the neutron power range is divided into smaller subranges because the neutron detector signal characteristics and the reference reactor power estimation methods are different for each subrange. Therefore, many factors should be considered when preparing the calibration procedure for DWRNPM channels. The main purpose of this work is to serve as a reference for performing the calibration of DWRNPM systems in research reactors. This work provides a comprehensive overview of the calibration of DWRNPM channels by describing the configuration of the DWRNPM system and by summarizing the theories of operation and the reference power estimation methods with their associated calibration procedure. The calibration procedure was actually performed during the commissioning of an open-pool type research reactor, and the results and experience are documented herein.