• Title/Summary/Keyword: 고속중성자

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Effect of Neutron irradiation in $Fe_{81}B_{13.5}_Si{3.5}C_2$Amorphous Ribbon (비정질 $Fe_{81}B_{13.5}_Si{3.5}C_2$ 리본의 중성자 조사에 따른 자기적 특성변화)

  • 김효철;홍권표;김철기;유성초
    • Journal of the Korean Magnetics Society
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    • v.10 no.2
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    • pp.49-52
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    • 2000
  • The changes of magnetic properties in neutron irradiated F $e_{81}$ $B_{13.5}$S $i_{3.5}$ $C_2$ amorphous ribbon were studied by X-ray diffraction, hysteresis loop, temperature dependence of magnetization and complex permeability. The fluences of thermal ( $n_{th}$) and fast ( $n_{f}$) neutron were 6.95$\times$10$^{18}$ $n_{th}$ c $m^{-2}$ and 4.56$\times$10$^{16}$ $n_{f}$c $m^{-2}$ , respectively. The changes of XRD Profiles were not observable at the neutron irradiated sample. The complex permeability spectra showed that the permeability from domain wall motion decreased due to the increase of pinning force against domain motion by the neutron irradiation, and the relaxation frequency of rotational magnetization moved to higher frequency region. The measurement of hysteresis loop showed the increase of magnetic softness, related to rotational magnetization, but saturation magnetization was decreased in neutron irradiation sample. The Curie temperature was decreased in the neutron irradiated sample.e.e.e.

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Neutron Shielding Performance of Mortar Containing Synthetic High Polymers and Boron Carbide (합성 고분자 화합물 및 탄화붕소 혼입에 따른 모르타르의 중성자 차폐성능 분석)

  • Min, Ji-Young;Lee, Bin-Na;Lee, Jong-Suk;Lee, Jang-Hwa
    • Journal of the Korea Concrete Institute
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    • v.28 no.2
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    • pp.197-204
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    • 2016
  • Concrete walls of neutron generating facilities such as fusion reactors and fission reactors become radioactive by neutron irradiation. Both low-activation and neutron shielding are a critical concern at the dismantling stage after the shutdown of facilities with a requirement of radioactive waste management. To tackle this, two types of additives were investigated in fabricating mortar specimens: synthetic high polymers and boron carbide. It is well known that a hydrogen atom is effective in neutron shielding by an elastic scattering because its mass is almost the same as that of the neutron. And boron is an effective neutron absorber with a big neutron absorption cross section. In this study, the effect of the type, shape, and size of polymers were investigated as well as that of boron carbide. Total 16 mix designs were prepared to reveal the effect of polymers on mechanical properties and neutron shielding performance. The neutron does equivalent of polymers-based mortar for fast neutrons decreased by 36 %, and the count rate of boron carbide-based mortar with regard to thermal neutrons decreased by 90 % compared to conventional mortar. These results showed that a combination of polymers and boron carbide compounds has potential to reduce the thickness of neutron shields as well as radioactive waste from reactors.

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

  • Kim, H.B.;Kim, H.S.;Kim, S.K.;Shin, D.H.;Yu, Y.B.;Ko, J.D.
    • Journal of the Korean Magnetics Society
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    • v.15 no.2
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    • pp.142-147
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    • 2005
  • The embrittlement of fast neutron-irradiated reactor pressure vessel (RPV) steels was investigated by X-ray diffraction patterns at room temperature and $M\ddot{o}ssbauer$ spectroscopy at room- and liquid nitrogen-temperature. Neutron fluence on the samples were $10^{12},\;10^{13},\;10^{14},\;10^{15},\;10^{16},\;10^{17},\;10^{18}\;n/cm^2$. The X-ray diffraction patterns showed that the structure of the neutron unirradiated sample was bcc type, where as but the neutron irradiated samples with the fluence higher than $10^{17}\;n/{\cal}cm^2$ were so severely damaged, that bcc type structure disappeared. The $M\ddot{o}ssbauer$ spectra of all samples showed superposition of two or more sextets. In this paper all $M\ddot{o}ssbauer$ spectra were fitted by three set of sextet. The isomer shift and quadrupole splitting values were found around zero. At liquid nitrogen temperature, magnetic hyperfine field and absorption area increase rapidly S 1 sextet in the samples of $10^{17}\~10^{18}\;n/{\cal}cm^2$ neutron fluences. And at room temperature, magnetic hyperfine field and absorption increased rapidly at SI sextet in the samples of $10^{17}\~10^{18}\;n/{\cal}cm^2$ neutron fluences. This rapid increase of magnetic hyperfine field and absorption area were inferred to be caused by the change of $^{56}Fe,\;^{55}Mn$ into $^{57}Fe$ due to by neutron irradiation.

Effects on the Magnetic Property Changes due to the defect in the Nuclear Reactor Vessel Material Irradiated by Fast Neutron (고속 중성자 조사에 의한 원자로 용기재료내의 결함생성이 자기적 특성변화에 미치는 영향)

  • Jeong, Myeong-Mo;Kim, Gil-Su;Jang, Gi-Sang;Yu, Geun-Bae;Park, Deok-Geun;Kim, Gil-Mu;Yun, In-Seop;Hong, Chi-Yu
    • Korean Journal of Materials Research
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    • v.9 no.12
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    • pp.1240-1244
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    • 1999
  • In order to assess the effects on the magnetic properties due to the defect in the material irradiated by fast neutron ranging $10^0-10^{18}n/cm^2$, the magnetic properties such as maximum magnetic induction, coercivity, remanence, Barkhausen Noise Amplitude(BNA), Barkhausen Noise Energy(BNE) and hardness were measured. It is shown that the magnetic properties and hardness do not change by the fast neutron irradiation under $10^{17}n/cm^2$. Therefore, in this experiment, it is understood that the magnetic properties decrease by the increase of hardness. This measurement method can be used to evaluate the neutron irradiation embrittlement nondestructively since the magnetic properties and hardness do change by the neutron irradiation over $10^{17}n/cm^2$ consistently.

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A Study on Neutron Shielding Capability Assessment of Metallic Hydride using Cf-252 Neutron Source (Cf-252 중성자 선원을 이용한 수소화금속의 중성자 방사선 차폐능 평가)

  • Yoo, Beong-Gyu;Kim, Keung-Sik;Kim, Yong-Soo
    • Journal of radiological science and technology
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    • v.26 no.3
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    • pp.51-57
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    • 2003
  • Mitigation of fast neutron irradiation damage on reactor vessel and improvement of mechanical integrity are desired for the successful plant life-time extension. In this study, the performance of metallic hydride for this application is reviewed and compared. First, selected prospective metallic hydrides are evaluated by MCNP code and put into the attenuation test using Cf-252 neutron source. Since for the reactor application high moderation and reflection with no absorption are favored, Z factor is introduced for the evaluation. According to the Z value estimation $ZrD_2$ and $TiD_2$ are turned out to be the most favorable fast neutron shielding materials. More thorough evaluation by computer simulation and experimentally, will be followed.

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

  • Lee, Sam-Lai;Chang, Kee-Ok;Kim, Byoung-Chul
    • Journal of the Korean Society for Nondestructive Testing
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    • v.21 no.3
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    • pp.307-312
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    • 2001
  • Ultrasonic signals from Charpy impact test specimen have been analyzed in order to evaluate the integrity of reactor pressure vessel. Base and weld metal that were extracted from reactor vessel doting plant outages according to the schedule of the surveillance test required by the related regulations have been used and the ultrasonic test parameters including velocity, attenuation, etc. showed a close correlations with the amount of neutron irradiation for base metal, relatively homogeneous materials. This result showed certain possibility where a nondestructive method could be used to predict the fluence of the Irradiation due to neutron in nuclear reactor vessel materials.

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경수로 압력용기 모의실험 PCA-REPLICA 차폐 벤치마크 해석

  • 길충섭;김정도;황원국
    • Proceedings of the Korean Nuclear Society Conference
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    • 1998.05a
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    • pp.163-168
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    • 1998
  • 경수로 압력용기의 취화는 주로 고속 중성자에 기인한다. 경수로 압력용기를 모의한 PCA-REPLICA실험을 해석하여 원자력 시설의 구조재로 쓰이는 철의 핵자료 검증과 MATXS/TRANSX/DANTSYS 계산체제의 유용성을 확인하고자 하였다. 라이브러리는 JEF-2.2를 이용한 KAFAX-F22가 기본 자료로 이용되었고, 이밖에 ENDF/B-Vl.1과 JENDI.-3.2의 철 핵자료도 비교 검증하였다. 계산결과는 실험오차 등을 고려하면 측정치와 근접하는 경향을 보였고, 앞으로 개발될 차폐해석용 라이브러리 검증에 유용한 자료가 될 수 있겠다.

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