• Title/Summary/Keyword: 에너지교정

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Investigation of Response of Several Neutron Surveymeters by a DT Neutron Generator (DT 중성자 발생기에 의한 중성자 검출기 반응도 조사)

  • Kim, Sang-In;Jang, In-Su;Kim, Jang-Lyul;Lee, Jung-Il;Kim, Bong-Hwan
    • Journal of Radiation Protection and Research
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    • v.37 no.1
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    • pp.35-40
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    • 2012
  • Several neutron measuring devices were tested under the neutron fields characterized with two distinct kinds of thermal and fast neutron spectrum. These neutron fields were constructed by the mixing of both thermal neutron fields and fast neutron fields. The thermal neutron field was constructed using by a graphite pile with eight AmBe neutron sources. The fast neutron field of 14 MeV was made by a DT neutron generator. In order to change the fraction of fast neutron fluence rate in each neutron fields, a neutron generator was placed in the thermal neutron field at 50 cm and 150 cm from the reference position. The polyethylene neutron collimator was used to make moderated 14 MeV neutron field. These neutron spectra were measured by using a Bonner sphere system with an LiI scintillator, and dosimetric quantities delivered to neutron surveymeters were determined from these measurement results.

Dose Evaluation of Neutron within Containment Building of a CE type Nuclear Power Plant (CE형 원전의 격납건물내 중성자선량 평가)

  • Kim Tae Wook;Han Jae Mun;Kim Kyung Doek;Yun Cheol Whan;Suh Jang Soo;Kim Young Jae
    • Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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    • v.3 no.1
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    • pp.23-30
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    • 2005
  • From measured results of the neutron fields at some principal places within the containment building in a CE type nuclear power plant in operation, the radiation exposure of a worker to the neutron at there was evaluated and the equivalent dose reflecting new recommendation (ICRP 60) was compared with that doing the old one (ICRP 26). The measured neutron field was also compared with calibration neutron field. From the analysis, the following conclusion was obtained: the average neutron radiation weighting factor according to new recommendation is 2.41 to 2.71 times higher than the old one. The average neutorn radiation weighting factor at the measured place was similar to that at calibration neutron field. The average neutron energy at measured place was between 42 and 158 keV and higher than that of calibration field of 500 keV. So, the measured equivalent dose in nuclear power plant could be overestimated compared to the real equivalent dose.

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Measurement of Detection Efficiency of Plastic Track Detector to ${\alpha}-particle$ (고체비적검출기의 알파선 검출효율 측정에 관한 연구)

  • Park, Young-Woong;Yang, Hyun-Soo
    • Journal of Radiation Protection and Research
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    • v.21 no.3
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    • pp.167-173
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    • 1996
  • The calibration method for the detection efficiency of solid state track detector to alpha is presented, and the detection efficiency of CN-85 and LEXAN to alpha is measured by this method. The results are 97% and 57% in CN-85 and LEXAN, respectively. The reason for a better result in CN-85 in not only the high sensitivity but also the low energy dependency with comparing for LEXAN. The peak detection efficiency is 3MeV and 1.8MeV in CN-85 and LEXAN, respectively.

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Development of Hydrogen Flow Field Standard in Hydrogen Refueling Station (수소충전유량 현장교정시스템의 개발 )

  • WOONG KANG;JINWOO SHIN;SAENG-HEE LEE;BYUNG-RO YOON;UNBONG BAEK
    • Transactions of the Korean hydrogen and new energy society
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    • v.33 no.6
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    • pp.684-691
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    • 2022
  • Hydrogen fuel cell electric vehicles are typically refueled at a wide range of temperatures (-40℃ to 85℃) in the hydrogen refueling station in accordance with the worldwide accepted standard. Currently, there is no traceable method by which to verify and calibrate the hydrogen flowmeters to be used at hydrogen refueling stations except for a water calibration process as a conventional method. KRISS hydrogen field test standard based on the gravimetric principle was developed to verify the measurement accuracy of the mass flowmeter to be used at hydrogen refueling stations for the first time in Korea.

Radioactive Neutron Source Calibration at the Korea Standards Research Institute (K-SRI 에서의 방사성 중성자 선원교정)

  • Hwang, Sun-Tae;Choi, Kil-Oung
    • Journal of Radiation Protection and Research
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    • v.10 no.1
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    • pp.67-73
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    • 1985
  • The manganous sulfate bath method for neutron source calibrations at the K-SRI is described together with the measurement of neutron emission rate of a source and the corrections applied for capture by competing nuclei of neutrons, and thermal neutron leakage, neutron absorption in the source itself. The commercially available neutron sources (Am-Be, $^{252}Cf$) for the calibration checks of neutron radiation instruments in the MeV range are considered in this paper.

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패 카운터 교정시 페내 방사능의 균일분포 가정에 따른 측정오차의 평가

  • 이태영;이종일;장시영;김종수
    • Proceedings of the Korean Nuclear Society Conference
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    • 1998.05b
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    • pp.612-617
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    • 1998
  • 폐부하량 측정에 사용되는 폐 카운터의 교정시 폐내 방사능의 균일분포 가정은 폐부하량 측정결과에 영향을 줄 것으로 예상된다. 따라서 본 연구에서는 균일분포 가정에 따른 측정오차를 평가하기 위해 몬데칼로시뮬레이션을 통해 분포패턴에 따른 계측효율을 구해 이률 비교·분석하였다. 그 결과 균일분포 패턴에 비해 17 keV에서 1.39배, 60 keV에서 1.14배, 185 keV에서 1.12배 까지 폐부하량이 과대평가되는 것으로 밝혀졌다 균일분포를 가정하더라도 문제가 될 정도로 과대평가가 되지 않음을 알 수 있었다. 반면, 과소평가는 17keV에서 50.2배, 60 keV에서 3.6배, 185 keV에서 2.7배 까지 나타나, 에너지가 작을수록 균일분포에 의한 교정에 문제의 심각성이 있는 것으로 보였다.

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Development of the laser measurement system for the wide output power range (광범위 출력 측정이 가능한 레이저 계측장치 개발)

  • Hwang Daeseok;Lee Young-Woo
    • Journal of the Korea Institute of Information and Communication Engineering
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    • v.9 no.8
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    • pp.1799-1804
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    • 2005
  • We have developed and estimated the measurement system of $CO_2$ and Nd:YAG laser power of wide range. The absorber is made of gold-plated copper cavity. The calibration heater is using a manganin(CuMn12Ni) coil, and output power is measured by using or resistance bridge with composed manganin and copper coil. Developed system can measure 5${\~}$1000W laser output power range. Calibration factors are 489.13J/mV at 100W and 497.04(J/mV) at 500W. correction factors are 0.99 at 100W and 1.006 at 500W.

Introduction to Daegwallyeong Wind Turbine Test Site and Field Test Study (대관령 풍력실증단지 및 실증연구 소개)

  • Yoo Neung-Soo;Nam Yun-Soo;Lee Jung-Wan
    • 한국신재생에너지학회:학술대회논문집
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    • 2005.06a
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    • pp.5-8
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    • 2005
  • This paper aims to introduce the Daegwallyeong wind turbine test site which is the first official wind turbine test site in Korea. The current status of test site, the characteristics, the projects performed and future plan of this test site are described. The results of wind condition measurements and monitoring system established by the Kangwon National University are presented. The importance of field test is also commented.

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영광 원자력발전소 원자로 건물내 중성자 스펙트럼 측정

  • 손중권;신상운;조찬희
    • Proceedings of the Korean Nuclear Society Conference
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    • 1998.05b
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    • pp.594-599
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    • 1998
  • 출력 운전중 원자로 건물내의 중성자 에너지 스펙트럼의 분포를 살펴보기 위해 중성자 스펙트럼 측정을 수행하였다. 영광4흐기 원자로 건물내 100ft 상에서 4곳, 122ft 상에서 4곳, 144 ft 상에서 8곳을 Bonner Multisphere Spectrometer(BMS) 시스템을 이용하여 중성자 스펙트럼을 측정하였다. BMS는 Cf-252 선원으로 교정하였으며 측정된 데이터는 BUNKI 코드를 이용하여 unfolding 하여 에너지 스펙트럼을 얻었다 분석 결과 100 ft의 경우 평균 중성자 에너지는 0.100 ~ 1.954 MeV, Fluence는 4.913$\times$$10^2$ ~ 1.478$\times$$10^4$ n/$\textrm{cm}^2$, 선량율은 0.56 ~ 289.37 mrem/hr의 분포를, 122 ft의 경우 평균 중성자 에너지는 0.122 ~ 0.320 MeV, Fluence는 4.586$\times$$10^{0}$ ~ 7.743$\times$$10^3$ n$\textrm{cm}^2$, 선량율은 0.05 ~ 201.46 mrem/hr의 분포를, 144 ft의 경우 평균 중성자 에너지는 0.062 ~ 0.578 MeV, Fluence는 7.922$\times$$10^{0}$ ~ 1.703$\times$$10^2$ n/$\textrm{cm}^2$, 선량율은 0.10 ~ 45.58 mrem/hr의 분포를 보였다.

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