• 제목/요약/키워드: Neutron fluence

검색결과 88건 처리시간 0.393초

초음파특성 분석에 의한 원자로 재료의 중성자 조사량 예측 (The Estimation of Neutron Fluence in Nuclear Reactor Vessel Materials by the Analysis of Ultrasonic Characteristics)

  • 이삼래;장기옥;김병철
    • 비파괴검사학회지
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    • 제21권3호
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    • pp.307-312
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    • 2001
  • 운전중인 원자로 재료의 건전성 평가를 위한 기계적 시험의 하나인 샤르피 충격 시험편에 대하여 초음파 신호분석이 이루어졌나 시험편으로는 모재와 용접재를 사용하였는데 이들 재료는 고온, 고압의 냉각수 및 지속적인 고속중성자가 방출되고 있는 가동중인 발전소에서 감시시험을 통한 원자로재료의 건전성평가를 목적으로 정지기간동안 인출된 깃이다. 분석결과 속도 및 감쇠와 같은 초음파 특성들이 재질이 비교적 균일한 모재에 있어서는 중성자 조사량과 밀접한 관련이 있는 것으로 보였으며 이를 활용하여 비파괴적인 방법으로 재료에 대한 중성자 조사량이 어느 정도인지를 예측할 수 있는 가능성을 보여주었다.

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Average and Effective Energies, and Fluence-Dose Equivalent Conversion Factors for $^{239}Pu-Be,\;^{241}Am-Li\;and\;^{241}Am-F$ Neutron Sources

  • Ro, Seung-Gy;Yoo, Young-Soo
    • Nuclear Engineering and Technology
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    • 제3권3호
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    • pp.155-160
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    • 1971
  • 중성자 검출기의 교정을 위한 기초자료를 제공할 목적으로 당 연구실에서 보유하고 있는 $^{239}$ Pu-Be, $^{241}$Am-Li 및 241Am-F 중성자선원에 대한 평균 및 유효에너지와 중성자당 등가선량 환산인자를 계산하였다. 이들은 중성자 스펙트럼 및 중성자의 에너지 함수로서 주어진 등가선량에 대한 여러 보고 자료에 따라 수치계산법을 도입하여 구해졌다. 그 계산결과는 $^{239}$ Pu-Be, $^{241}$Am-Li 및 $^{241}$Am-F 순서로 각각 다음과 같이 주어진다 1. 평균에너지 4.07$\pm$0.33, 0.42 및 1.41 MeV; 2. 중성자의 단일충돌과정에 의하여 인체가 받게되는 선량의 개념에 따라 구한 유효에너지 4.45$\pm$0.344, 0.51 및 1.47 MeV; 3. 중성자의 다중충돌과정에 의하여 인체가 받게되는 선량의 개념에 따라 구한 유효에너지 4.50$\pm$0.36, 0.50 및 1.45 MeV; 4. 중성자당 단일충돌 등가선량 환산인자 (2.74$\pm$0.07)$10^{-8}$ , 1.58$\times$ $10^{-8}$ 및 2.34$\times$$10^{-8}$ rems/(n/$\textrm{cm}^2$); 5. 중성자당 다중충돌 등가선량 환산인자 (3.55$\pm$0.09)$10^{-8}$ , 2.19$\times$$10^{-8}$ 및 2.82$\times$$10^{-8}$ rems/(n/$\textrm{cm}^2$).

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Microstructure and Mechanical Property of Irradiated Zr-2.5Nb Pressure Tube in Wolsong Unit-1

  • 김영숙;안상복;오동준;김성수;정용무
    • 소성∙가공
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    • 제8권3호
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    • pp.241-241
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    • 1999
  • With the aim of assessing the degradation of Zr-2.5Nb pressure tubes operating in the Wolsong unit-1 nuclear power plant, characterization tests are being conducted on irradiated Zr-2.5Nb tubes removed after 10-year operation. The examined tube had been exposed to temperatures ranging from 264 to 306℃ and a neutron fluence of 8.9×$10^{21}$ n/cm²(E>1 MeV) at the maximum. Tensile tests were carried out at temperatures ranging from RT to 300℃. The density of a-type and c-type dislocations was examined on the irradiated Zr-2.5Nb tube using a transmission electron microscope. Neutron irradiation up to 8.9×$10^{21}$ n/cm²(E>1 MeV) yielded an increase in a-type dislocation density of the Zr-2.5Nb pressure tube to 7.5×$10^{14} m^{-2}$, which was highest at the inlet of the tube exposed to the low temperature of 275℃. In contrast, the c-component dislocation density did not change with irradiation, keeping an initial dislocation density of 0.8×$10^{14} m^{-2}$ over the whole length of the tube. As expected, the neutron irradiation increased mechanical strength by about 17-26% in the transverse direction and by 34-39% in the longitudinal direction compared to that of the unirradiated tube at 300℃. The change in the mechanical properties with irradiation is discussed in association with the microstructural change as a function of temperature and neutron fluence.

The effect of neutron irradiation on hydride reorientation and mechanical property degradation of zirconium alloy cladding

  • Jang, Ki-Nam;Kim, Kyu-Tae
    • Nuclear Engineering and Technology
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    • 제49권7호
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    • pp.1472-1482
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    • 2017
  • Zirconium alloy cladding tube specimens were irradiated at $380^{\circ}C$ up to a fast neutron fluence of $7.5{\times}10^{24}n/m^2$ in a research reactor to investigate the effect of neutron irradiation on hydride reorientation and mechanical property degradation. Cool-down tests from $400^{\circ}C$ to $200^{\circ}C$ under 150 MPa tensile hoop stress were performed. These tests indicate that the irradiated specimens generated a smaller radial hydride fraction than did the unirradiated specimens and that higher hydrogen content generated a smaller radial hydride fraction. The irradiated specimens of 500 ppm-H showed smaller ultimate tensile strength and plastic strain than those characteristics of the 250 ppm-H specimens. This mechanical property degradation caused by neutron irradiation can be explained by tensile hoop stress-induced microcrack formation on the hydrides in the irradiation-damaged matrix and subsequent microcrack propagation along the hydrides and/or through the matrix.

Turn-off time improvement by fast neutron irradiation on pnp Si Bipolar Junction Transistor

  • Ahn, Sung Ho;Sun, Gwang Min;Baek, Hani
    • Nuclear Engineering and Technology
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    • 제54권2호
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    • pp.501-506
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    • 2022
  • Long turn-off time limits high frequency operation of Bipolar Junction Transistors (BJTs). Turn-off time decreases with increases in the recombination rate of minority carriers at switching transients. Fast neutron irradiation on a Si BJT incurs lattice damages owing to the displacement of silicon atoms. The lattice damages increase the recombination rate of injected holes with electrons, and decrease the hole lifetime in the base region of pnp Si BJT. Fast neutrons generated from a beryllium target with 30 MeV protons by an MC-50 cyclotron were irradiated onto pnp Si BJTs in experiment. The experimental results show that the turn-off time, including the storage time and fall time, decreases with increases in fast neutron fluence. Additionally, it is confirmed that the base current increases, and the collector current and base-to-collector current amplification ratio decrease due to fast neutron irradiation.

SPECTRUM WEIGHTED RESPONSES OF SEVERAL DETECTORS IN MIXED FIELDS OF FAST AND THERMAL NEUTRONS

  • Kim, Sang In;Chang, Insu;Kim, Bong Hwan;Kim, Jang Lyul;Lee, Jung Il
    • Nuclear Engineering and Technology
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    • 제46권2호
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    • pp.273-280
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    • 2014
  • The spectrum weighted responses of various detectors were calculated to provide guidance on the proper selection and use of survey instruments on the basis of their energy response characteristics on the neutron fields. To yield the spectrum weighted response, the detector response functions of 17 neutron-measuring devices were numerically folded with each of the produced calibration neutron spectra through the in-house developed software 'K-SWR'. The detectors' response functions were taken from the IAEA Technical Reports Series No. 403 (TRS-403). The reference neutron fields of 21 kinds with 2 spectra groups with different proportions of thermal and fast neutrons have been produced using neutrons from the $^{241}Am$-Be sources held in a graphite pile, a bare $^{241}Am$-Be source, and a DT neutron generator. Fluence-average energy ($E_{ave}$) varied from 3.8 MeV to 16.9 MeV, and the ambient-dose-equivalent rate [$H^*(10)/h$] varied from 0.99 to 16.5 mSv/h.

상온 및 액체질소 온도에서 고속 중성자 조사된 원자로 압력 용기의 취화 현상에 관한 연구 (A Study on Embrittlement of Fast Neutron-irradiated Nuclear Reactor Pressure Vessel Steels at Room- and Liquid Nitrogen-temperature)

  • 김형배;김형상;김순구;신동훈;유연봉;고정대
    • 한국자기학회지
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    • 제15권2호
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    • pp.142-147
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    • 2005
  • 고속 중성자 조사한 원자로 압력 용기의 취하현상을 상온에서 X-선 회절 실험과 액체 질손 온도에서 M$\ "{o}$ssbauer 분광법으로 조사하였다. 시료의 중성자 조사량은 $10^{12},\;10^{13},\;10^{14},\;10^{15},\;10^{16},\;10^{17},\;10^{18}\;n/{\cal}cm^2$이다. X-선 회절 패턴에서 중성자 조사하지 않은 시료는 bcc 형태를 나타내었으나, 중성자 조사량이 $10^{17}\;n/{\cal}cm^2$ 이상인 시료에서는 bcc 구조가 사라지는 심각한 손상을 보였다. 모든 시료의 $M\ddot{o}ssbauer$ 스펙트럼은 두개 혹은 그 이상의 sextet의 중첩을 보였다. 모든 $M\ddot{o}ssbauer$ 스펙트럼은 본문에서는 3조의 sextet로 fitting 하였다. 이성질체 이동치와 사중극자 분열치는 거의 영에 가까운 값을 나타내었다. 액체 질소 온도에서 중성자 조사량이 $10^{17}\~10^{18}\;n/{\cal}cm^2$인 시료에서 S1 sextet의 초미세 자기장과 흡수 면적이 급격히 상승하는 현상을 관측하였으며, 상온에서 또한 이 현상을 관측하였다. 이는 중성자 조사에 의한 시료 내부의 $^{55}Mn$ 혹은 $^{56}Fe$$^{57}Fe$의 천이에 의한 $^{57}Fe$$M\ddot{o}ssbauer$ 핵종의 증가에 기인하는 것으로 추측된다.

중성자조사재료의 acoustic Barkhausen noise의 harmonic frequency 분석 (Harmonic frequency analysts of acoustic Barkhausen noise on neutron irradiated material)

  • 심철무;박승식;구길모;손재민;이창희
    • 한국음향학회:학술대회논문집
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    • 한국음향학회 1999년도 학술발표대회 논문집 제18권 2호
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    • pp.401-406
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    • 1999
  • In relation to a non-destructive evaluation of irradiation damages of micro-structure interstitial, void and dislocation, the changes in the hysteresis loop, Barkhausen noise amplitude and the harmonics frequency due to a neutron irradiation were measured and evaluated. The Mn-Mo-Ni low alloy steel of RPV was irradiated to a neutron fluence of $2.3\times10^{19}\;n/cm^2\;(E\geq1\;MeV)\;at\;288^{\circ}C$. The saturation magnetization of neutron irradiated metal did not change. The neutron irradiation caused the coercivity to increase, whereas susceptibility to decrease. The amplitude of Barkhausen noise parameters associated with the domain wall motion were decreased by a neutron irradiation. The spectrum of Barkhausen noise is analysed with an applied frequency of 4 Hz and 8 Hz, sampling time of $50\;{\mu}sec\;and\;20\;{\mu}sec$. The harmonic frequency shows 4 Hz, 8 Hz, 12 Hz; and 16 Hz reflected from an unirradiated specimen. On the contrary, the harmonic frequency disappeared on the irradiated specimen.

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The Analysis of Spectrum on the Barkhausen Noise of Hysteresis Loops on Neutron Irradiated Material

  • Sim, Cheul-Muu;Chang, Kee-Ok;Park, Kook-Nam;Cho, Man-Soon;Park, Chang-Oong
    • The Journal of the Acoustical Society of Korea
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    • 제18권1E호
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    • pp.7-12
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    • 1999
  • In relation to a non-destructive evaluation of irradiation damages, the changes in the hysteresis loop and Barkhausen noise amplitude and the harmonics frequency due to a neutron irradiation were measured and evaluated. The Mn-Mo-Ni low alloy steel of RPV was irradiated to a neutron fluence of 2.3 ×10/sup 19/ n/㎠ (E ≥1 MeV) at 288℃. The saturation magnetization of neutron irradiated metal did not change. The neutron irradiation caused the coercivity to increase, whereas susceptibility to decrease. The amplitude of Barkhausen noise parameters associated with the domain wall motion were decreased by a neutron irradiation. The spectrum of Barkhausen noise is analysed with an applied frequency of 4 Hz and 8 Hz, sampling time of 50 μ sec and 20 μ sec. The harmonic frequency shows 4 Hz, 8 Hz, 12 Hz and 16 Hz reflected from an unirradiated specimen. On the contrary, the harmonic frequency disappeared on the irradiated specimen. In addition to the amplitude, the harmonic frequency of Barkhausen noise is taken into accounts as a promising tool for monitoring the irradiation induced degradation of the reactor materials such as a SA508 of PWR-RPV steel and a Zr₄ of HANARO-CNH.

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