• 제목/요약/키워드: prompt gamma activation analysis

검색결과 18건 처리시간 0.05초

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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    • 제48권2호
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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%.

Performance of a Compton Suppression Spectrometer of the SNU-KAERI PGAA Facility

  • Sun Gwang Min;Park Chang Su;Choi H.D.
    • Nuclear Engineering and Technology
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    • 제35권4호
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    • pp.347-355
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    • 2003
  • The \gamma-ray spectrometer of the PGAA (Prompt Gamma Activation Analysis) facility constructed at HANARO of the Korea Atomic Energy Research Institute was upgraded to the multi-mode spectrometer including the single mode, the Compton suppression mode and the pair mode. The performance of the spectrometer was tested and summarized. The background count rate and the uncertainty of the detection efficiency were reduced greatly in comparison with those before the new installation.

Beam Characteristics of Polychromatic Diffracted Neutrons Used for Prompt Gamma Activation Analysis

  • S. H. Byun;G. M. Sun;Park, H. D.
    • Nuclear Engineering and Technology
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    • 제34권1호
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    • pp.30-41
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    • 2002
  • The neutron beam is fully characterized for the prompt gamma activation analysis facility at Hanaro in the Korea Atomic Energy Research Institute(KAERI). The facility uses thermal neutrons which are diffracted vertically from a horizontal beam port by a set of pyrolytic graphite(PG) crystals positioned at the Bragg angle of 45" Neutron spectra, neutron flux and Cd-ratio are determined for the three extraction modes of diffracted beam by means of the theoretical and experimental efforts. To obtain theoretical result, the reflectivity of pyrolytic graphite is calculated in the diffraction model for mosaic crystal and the angular divergence after diffraction by mosaic crystal is estimated from Monte Carlo simulation. The time-of-flight spectrometer and gold activation wire are used for measuring the neutron spectra. Both the calculated and measured spectra have proven that the unique feature of polychromatic beam obtained by PG crystals are useful for PGAA. The thermal neutron flux of 7.9$\times$107 n/cm$^2$s and the Cd-ratio of 266 for gold have been achieved at the sample position while the reactor operates at 24 MW The uniformity of beam flux is 12% in the central 1$\times$1 cm$^2$ area. Finally, the beam is briefly characterized by the effective velocity and temperature which are determined by measuring the prompt Y-ray spectra for thin and thick boron samples.ples.

Design, construction, and characterization of a Prompt Gamma Neutron Activation Analysis (PGNAA) system at Isfahan MNSR

  • M.H. Choopan Dastjerdi;J. Mokhtari;M. Toghyani
    • Nuclear Engineering and Technology
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    • 제55권12호
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    • pp.4329-4334
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    • 2023
  • In this research, a prompt gamma neutron activation analysis (PGNAA) system is designed and constructed based on the use of a low power research reactor. For this purpose, despite the fact that this reactor did not include beam tubes, a thermal neutron beam line is installed inside the reactor tank. The extraction of the beam line from inside the tank made it possible to provide the neutron flux from the order of 106 n.cm-2.s-1. Also, because the beam line is installed in a tangential position to the reactor core, its gamma level has been minimized. Also, a suitable radiation shield is considered for the detector to minimize the background radiation and prevent radiation damage to the detector. Calculations and measurements are done in order to characterize this system, as well as spectrometry of several samples. The results of evaluations and experiments show that this system is suitable for performing PGNAA.

중성자 핵반응을 이용한 원소 검출기술 - 즉발감마선 중성자 방사화분석법을 이용한 검출기술 - (Elemental Analysis by Neutron Induced Nuclear Reaction - Prompt Gamma Neutron Activation Analysis for Chemical Measurement -)

  • 송병철;박용준;지광용
    • 분석과학
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    • 제16권5호
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    • pp.1041-1051
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    • 2003
  • 즉발감마선 중성자방사화법 (PGAA)은 시료내 미량 및 주원소를 빠르게 비파괴적으로 분석하는 방법으로 주로 광물, 금속, 석탄, 시멘트, 석유, 코팅, 제지 등 다양한 산업체에서 실시간 분석법으로 매우 유용하다. 이 방법은 제약과 관련된 산업체 또는 연구업무에도 활용되며, 마약 또는 폭발물과 같은 위험물질의 탐지에도 이용되고 있다. 본 총설은 즉발감마선 중성자 방사화법의 현재의 기술현황과 앞으로 연구추진 경향에 대하여 서술하였다. PGAA 시스템은 중성자 선원, 증성자 핵반응으로부터 발생하는 즉발감마선을 측정하기위한 다중채널분석기와 A/D 변환기 등의 전자모듈과 고분해능 HPGe 검출기로 구성된다. 속중성자의 콤프턴 산란에 의한 높은 바탕값은 감마-감마 동시계수장치의 도입으로 개선될 수 있다. 현재 $^{252}Cf$를 사용한 즉발감마선 중성자 방사화 장치는 수용액중에 존재하는 원소들의 실시간분석을 위해 한국원자력연구소에서 개발중에 있다. 이 장치는 다양한 마약 및 폭발물 또는 화학무기의 탐지에도 응용될 수 있다.

Determining PGAA collimator plug design using Monte Carlo simulation

  • Jalil, A.;Chetaine, A.;Amsil, H.;Embarch, K.;Benchrif, A.;Laraki, K.;Marah, H.
    • Nuclear Engineering and Technology
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    • 제53권3호
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    • pp.942-948
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    • 2021
  • The aim of this work is to help inform the decision for choosing a convenient material for the PGAA (Prompt Gamma Activation Analysis) collimator plug to be installed at the tangential channel of the Moroccan Triga Mark II Research Reactor. Two families of materials are usually used for collimator construction: a mixture of high-density polyethylene (HDPE) with boron, which is commonly used to moderate and absorb neutrons, and heavy materials, either for gamma absorption or for fast neutron absorption. An investigation of two different collimator designs was performed using N-Particle Monte Carlo MCNP6.2 code with the ENDF/B-VII.1 and MCLIP84 libraries. For each design, carbon steel and lead materials were used separately as collimator heavy materials. The performed study focused on both the impact on neutron beam quality and the neutron-gamma background at the exit of the collimator beam tube. An analysis and assessment of the principal findings is presented in this paper, as well as recommendations.

Experimental setup for elemental analysis using prompt gamma rays at research reactor IBR-2

  • Hramco, C.;Turlybekuly, K.;Borzakov, S.B.;Gundorin, N.A.;Lychagin, E.V.;Nehaev, G.V.;Muzychka, A. Yu;Strelkov, A.V.;Teymurov, E.
    • Nuclear Engineering and Technology
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    • 제54권8호
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    • pp.2999-3005
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    • 2022
  • The new experimental setup has been built at the 11b channel of the IBR-2 research reactor at FLNP, JINR, to study the elemental composition of samples by registration of prompt gamma emission during thermal neutron capture. The setup consists of a curved mirror neutron guide and a radiation-resistant HPGe high-purity germanium detector. The detector is surrounded by lead shielding to suppress the natural background gamma level. The sample is placed in a vacuum channel and surrounded by a LiF shield to suppress the gamma background generated by scattered neutrons. This work presents characteristics of the experimental setup. An example of hydrogen concentration determining in a diamond powder made by detonation synthesis is given and on its basis, the sensitivity of the setup is calculated being ~4 ㎍.

즉발감마선방사화분석법에 의한 철강시료 중의 붕소 측정 (Determination of trace boron in steels by prompt gamma-ray activation analysis)

  • 김인중;조경행
    • 분석과학
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    • 제22권4호
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    • pp.302-306
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    • 2009
  • 철강 중의 미량 붕소는 소재의 기계적, 물리적 특성에 중요한 영향을 준다. 즉발감마선 방사화 분석법에 의해 저합금강 시료 중의 미량 붕소를 측정하였다. 시료는 한국표준과학연구원에서 제조한 저합금강 표준물질KRISS 101-01-C21~C26을 이용하였으며, 측정방법의 유효성 확인을 위해 NIST SRM 362, 364, 1761, 1762를 정확도관리용 시료로 사용하였다. NIST SRM 362를 제외하고는 측정 농도가 인증값의 불확도 범위내에서 잘 일치하였다. 불확도는 ISO guideline에 따라 평가하였으며, 포함인자 2를 적용하여 확장불확도를 산출하였다. 붕소 농도 mg/kg수준에서 상대확장불확도는 3%에서 7% 사이였다. 그 결과를 용매추출-유도결합플라스마 방출분광분석결과와 비교하여 제시하였다.