• 제목/요약/키워드: 중성자별

Search Result 50, Processing Time 0.028 seconds

중성자별 이중성 EXO 0331+530의 관측연구

  • Kim, Sun-Uk
    • 한국지구과학회:학술대회논문집
    • /
    • 2010.04a
    • /
    • pp.114-114
    • /
    • 2010
  • 중성자별을 포함하는 이중성인 EXO 0331+350을 가시광선 및 자외선으로 관측하였다. EXO 0331+350은 전형적인 Be/X-선 이중성인 것처럼 보이지만 특이하게도 공전 주기상의 근일점 마다 매우 밝아지는 다른 Be/X-선 이중성들과는 확연히 다르게 밝아지는 시기가 매우 불규칙하다. 따라서 그 물리적인 기작을 연구하기 위해서는 오랜 기간의 모니터링이 필수적이다.

  • PDF

Development of Neutron Detectors with an Optimal Sensitivity on the Geometric Analysis (구조별 특성분석을 통한 최적감도의 중성자 측정센서 개발)

  • Lee, Nam-Ho;Hwang, Young-Gwan;Youk, Yong-Ho;Nam, Seung-Man;Lee, Hong-Kyu
    • Proceedings of the KIEE Conference
    • /
    • 2009.07a
    • /
    • pp.1696_1697
    • /
    • 2009
  • 실리콘형 다이오드가 중성자에 노출되면 소자 내부에서 변위손상 발생으로 인한 저항의 변화현상이 발생하며, 이 변화량은 피폭된 중성자의 선량과 비례관계에 있다. 단위 중성자 피폭량에 대한 소자의 저항성 변화량은 감도로 표현되며 감도의 크기는 측정하려는 용도에 적합하게 조절되어야만 활용도를 높일 수 있다. 본 연구에서는 군용 중성자 탐지소자로 활용할 중성자 탐지소자로서 다양한 구조의 핀 다이오드를 제작하고 구조에 따른 중성자 감도를 분석하여 최적의 감도를 가지는 조건을 설정하고 개별소자 형태의 반도체 소자를 제작하였다. 제작된 소자의 중성자탐지능은 측정범위내에서 우수한 선형성을 보였고 온도에 대한 의존성 시험에서 안정적인 특성을 나타내었다.

  • PDF

Calculation of Neutron Energy Distribution from the Components of Proton Therapy Accelerator Using MCNPX (MCNPX를 이용한 양성자 치료기의 구성품에서 발생하는 중성자 에너지 분포계산)

  • Bae, Sang-Il;Shin, Sang-Hwa
    • Journal of the Korean Society of Radiology
    • /
    • v.13 no.7
    • /
    • pp.917-924
    • /
    • 2019
  • The passive scattering system nozzle of the proton therapy accelerator was simulated to evaluate the neutrons generated by each component in each nozzle by energy. The Monte Carlo N-Particle code was used to implement spread out Bragg peak with proton energy 220 MeV, reach 20 cm, and 6 cm length used in the treatment environment. Among the proton accelerator components, neutrons were the highest in scatterers, and the neutron flux decreased as it moved away from the central flux of the proton. This study can be used as a basic data for the evaluation of the radiation necessary for the maintenance and dismantling of proton accelerators.

Effects of Combined Irradiation of Neutrons and ${\gamma}$-Rays on the Pink Mutation Frequencies in Tradescantia (중성자와 감마선 중복 조사가 자주달재비 분홍돌연변이율에 미치는 영향)

  • Kim, Jin-Kyu;Lee, Young-Keun;Kim, Jae-Sung;Shin, Hae-Shick;Hyun, Soung-Hee
    • Journal of Radiation Protection and Research
    • /
    • v.25 no.2
    • /
    • pp.67-73
    • /
    • 2000
  • The effects of combined irradiation of neutrons and ${\gamma}$-rays were analysed by means of Tradescantia stamen hair (TSH) assay. Potted plants were irradiated with $0{\sim}2$ Gy of ${\gamma}$-rays. For the combined treatments, the plants were irradiated with neutrons from $^{252}Cf$ 24 hours before or after ${\gamma}$-irradiation. The slopes of dose-response curves were 5.98, 6.17 and 7.48, in ${\gamma}$-rays, ${\gamma}$-rays+neutrons, and neutrons+${\gamma}$ -rays irradiated groups, respectively. The biological efficacy of radiations in the induction of pink mutations increased by 25% in neutrons+${\gamma}$-rays irradiated group, while it increased by 12% in ${\gamma}$-rays+neutrons irradiated group. The combined irradiation with two kinds of radiations results in the different efficacy of radiation depending on the order of irradiations, which is of great importance in the related fields such as sterilization and radiotherapy.

  • PDF

외뿔소자리 신성 1975의 다단계 분출 현상의 이론적 고찰

  • Kim, Sun-Uk
    • 한국지구과학회:학술대회논문집
    • /
    • 2010.04a
    • /
    • pp.117-117
    • /
    • 2010
  • 외뿔소자리 신성 1975는 발견 당시에는 백색왜성과 적색왜성의 근접쌍성계인 것으로 알려졌으나, 엑스선 관측과 그에 따른 표준 정류 상태 원반 모형에 근거한 해석으로 중성자별 또는 블랙홀의 가능성이 대두되었다. 곧이어, 광학관측에 의하여 블랙홀 이중성임이 간접적으로 동정되었다. 최근 들어 1975젼 당시의 많지 않은 전파 관측 자료들을 재해석하여 상대론적인 물질 분출 현상, 즉 마이크로퀘이사 현상이 있었을 가능성이 관측적으로 제시되었다. 우리는 시간 종속적 열적 불안정성 모형을 바탕으로 수치모형을 계산하여 관측적으로 제시된 물질분출의 가능성을 이론적으로도 제시할 수 있음을 보인다

  • PDF

Effects of Fission Neutron Spectra in Reactor Calculations (핵분열 중성자스펙트럼이 핵계산에 미치는 영향)

  • 김정도;이종태
    • Nuclear Engineering and Technology
    • /
    • v.15 no.4
    • /
    • pp.280-285
    • /
    • 1983
  • Effects of fission neutron spectra in the reactor calculations have been analysed through applications of several cases of spectra in the criticality calculations of fast critical assemblies. They were the application of Maxwellian or Watt-Cranberg type formulae, of region dependent spectrum, of composition dependent spectrum, of fission transfer matrix, and the effects due to the selection of nuclear temperature in Maxwellian formula.

  • PDF

Investigation of the Control Absorber Characteristics in the KMRR (KMRR의 제어흡수체 특성에 관한 연구)

  • Hark Rho Kim;Young Jin Kim;Jung-Do Kim
    • Nuclear Engineering and Technology
    • /
    • v.21 no.3
    • /
    • pp.151-164
    • /
    • 1989
  • Since in the KMRR the neutron spectrum is hardened in comparison with the conventional power reactors, and the absorber is in a tube-form which may contain the neutron multiplying media inside it, the reactor physics characteristics of the KMRR absorber are much different. The characteristics of the hafnium control absorber are studied under the several kinds of the environmental conditions. The environmental conditions include the inner materials inside the absorber shroud, the absorber thickness, the absorber burnout, and the fuel burnup. Investigated are nuclear characteristics such as the dependence of the spectral, regional, and isotopic contribution to the neutron absorption, and the dependence of the reactivity worth. Many important absorber characteristics are identified and presented from the analysis.

  • PDF

DUPIC 핵연료 보장조치용 중성자측정장치 개발(II)

  • 이영길;차홍렬;김호동;강희영;홍종숙
    • Proceedings of the Korean Nuclear Society Conference
    • /
    • 1997.05b
    • /
    • pp.356-361
    • /
    • 1997
  • DUPIC 공정의 핵연료에 대핀 핵물질 보장조치(safeguards)를 이행하여 핵투명성(nuclear transparency)을 검증하기 위한 중성자측정장치를 개발하였다. 본 장치를 사용한 보장조치 원리 및 기술적 사항, 장치 설계 개념 등에 관해서는 본 논문의 전편$^{[1]}$ 에서 기술하였고 여기서는 제작된 측정장계에 대한 성능시험 내용을 중심으로 나타내었다. 즉, 일반시설(cold lab.)내에서 실시한 성능시험 결과로부터 장치의 각 부분별 기능이 정상적으로 작동되고 있음을 확인할 수 있었으며 이것은 현재 후속과정으로 핫셀(hot cell)내에서 사용후핵연료를 이용하여 수행중인 성능시험 결과를 분석하는 기본자료로 활용될 것이다. 본 장치 개발을 통하여 확보한 중성자측정 기술은 앞으로 고준위감마선방출 핵물질을 사용하는 후행핵연료주기 시설에 대한 핵물질 통제 및 계량관리에 필요한 보장조치 기술로 활용될 수있을 것으로 기대된다..

  • PDF

A Study on the Wigner Energy Release Characteristics of Irradiated Graphite of KRR-2 (연구로 2호기 중성자 조사 흑연의 Wigner 에너지 방출 특성 연구)

  • Jeong Gyeong-Hwan;Yun Sei-Hun;Lee Dong-Gyu;Jung Chong-Hun;Lee Keun-Woo
    • Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
    • /
    • v.4 no.3
    • /
    • pp.209-216
    • /
    • 2006
  • Characteristics of heat release process, while the Wigner energy was drawn off the graphite during DSC(Differential Scanning Calorimenter) measurement as an example of annealing process which is one of release methods of Wigner energy that is contained in the irradiated graphite, was studied. Linear temperature rise method in DSC operation was selected to estimate the total Wigner energy content and the heat release rate of each graphite samples, which were located in several positions in the thermal column in KRR-2 research reactor. As an annealing process in DSC operation Wigner energy of the irradiated graphite samples were totally released by heat supplying to the graphite from room temperature to $500^{\circ}C$, in DSC. Characteristics of Wigner energy release from the graphite sample was well correlated with the various activation energy model of the kinetic equation.

  • PDF

Preliminary Study of Cosmic-ray Shielding Material Design Using Monte-Carlo Radiation Transport Code (몬테카를로 방사선 수송 모델을 활용한 우주방사선 차폐체 설계 관련 선행연구)

  • Kang, Chang-Woo;Kim, Yeong-Chan
    • Journal of the Korean Society of Radiology
    • /
    • v.16 no.5
    • /
    • pp.527-536
    • /
    • 2022
  • The radiation shielding characteristic of neutron shielding material has been studied as the preliminary study in order to design cosmic-ray shielding material. Specially, Soft Magnetic Material, known to be effective in EMP and radiation shielding, has been investigated to check if the material would be applicable to cosmic-ray shielding. In this work, thermal neutron shielding experiment was conducted and the Monte Carlo N-Particle(MCNP) was applied to employ skymap.dat, which is cosmic-ray data embedded in MCNP. As a result, polyethylene, borated polyethylene, and carbon nano tube, containing carbon or hydrogen, have been found to be effective in reduction of neutron flux below 20 MeV (including thermal, epithermal, evaporation). In contrast, the materials composed of iron such as SS316 and Soft Magnetic Material show a good shielding performance in the cascade energy range (above 20 MeV). Since Soft Magnetic Material is consisting of 13% of boron, it can also decrease thermal neutron flux, so it is expected that it would show a significant reduction on the entire range of neutron energy if the Soft Magnetic Material is used with hydrogen and carbon, so called low Z material.