NE-213 섬광검출기의 감마선 Compton edge 조사

李三烈,閔永基,盧泰翊 東亞大學校 大學院 1993 大學院論文集 Vol.18 No.-

The Compton edge of the Compton distribution of a NE-213 detector to 0.662 MeV(?Cs) and 0.835 Mev(?Mn) gamma-rays were investigated by means of the coincidence method. The Compton edge position for ?Cs and ?Mn gamma-rays were 8.9 and 5.1 percent above the peak of the compton distribution spectrum, respectively. The experiment results were compared with calculated ones.

중성자 collimator의 제작 및 Am-Be 중성자 파고스펙트럼 측정

윤정란,노태익,민영기,이삼열 東亞大學校 1997 東亞論叢 Vol.34 No.-

The neutron collimator, 20cm width, 30cm length, 15cm height and 1cm diameter of hole was constructed by using polyethylene block which includes 15% boric acid. The total cross section of average 7.7MeV neutrons for Al, Cu, Au, Pb samples and the scattering angular distribution of the same energy for Al sample were measured by using 10mCi Am-Be fast neutron source. The range of average 7.7MeV neutron energy were selected from 6.45 MeV to 8.95MeV at the measured pulse height spectrum.2"Φ×2" NE-213 organic liquid scintillation detector was used on the measurement of neutron flux. The Pulse Shape Discrimination(P.S.D.) methods were used for the spectra separation of neutron with r-ray at the mixed field. The results of measurement of total cross section and scattering angular distribution for average 7.7MeV neutrons were compared with other researcher’ and ENDF/B-VI, respectively.

^161, ^163Dy의 0.003eV~50keV의 중성자 포획 단면적 측정

민영기,윤정란,노태익,김귀년,이삼열 東亞大學校附設基礎科學硏究所 2002 基礎科學硏究論文集 Vol.19 No.1

교토대학 원자로 연구소의 46MeV 전자선형가속기를 사용하여 중성자 TOF 방법으로, 에너지 영역 0.003eV∼50keV의 ^161, 163Dy sample의 중성자 포획 단면적을 측정하였다. 본 실험에서 사용된 Bi_4Ge_3O_12(BGO) 섬광 검출기는 sample의 핵반응에서 나오는 즉발 포획 감마선 측정에 사용하였다. 이 검출기는 중성자 선원으로부터 거리 12.7±0.02m 위치에 12개의 블록으로 되어 있으며, sample에 포획되는 중성자 flux의 절대치를 구하기 위해 Sm(n, γ) 및 ^10B(n, αγ) 반응을 이용하였다. ^161, 163Dy에 대한 포획 단면적 측정결과는 ENDF/B-VI 결과와 비교하였다. The neutron capture cross sections of ^161, 162Dy has been measured in the energy region from 0.003eV 50keV by using the neutron time-of-flight(TOF) promptγmethod with a 46MeV electron linear accelerator at the Research Reactor Institute, Kyoto University. An assemble of twelve pieces of BGO scintillation detectors, which was placed at a distance of 12.7±0.02mm from the neutron source, was employed as a total energy absorption detector for the prompt capture gamma-ray measurement, to obtain the absolute capture cross section value. The sample of ^161, 163Dy is a form of metallic plate. An enriched boron sample was employed to monitor the neutron flux/spectrum of the TOF beam using the standard reference cross section of the ^10B(n, αγ) reaction. Previous measurements and evaluated data in ENDF/B-VI was compared with the present results.

Am-Be 선원을 통한 중성자의 전단면적 측정

민영기,오선영,노태익,박상태,이대원,이삼열 東亞大學校 1996 東亞論叢 Vol.33 No.-

Total cross sections was measured for 6.45MeV∼8.96MeV (average 7.7MeV) neutron on ??, ??, ?? absorber using ?? fast neutron source. The 2" ø×2" NE-213 organic liquid scitillation detector was used as a spectrometer of neutrons and gamma-rays. The zero crossing time analysis method was introduced in order to obtain the pulse heigh spectrum of neutrons and n-γ pulse-shape spectrum was investigated. The ratio of neutron peak for a Vally was 1:20. The total cross section resulting from the experiment enabled us to suppose a optical model as a neutron model, obtain the radius of a nuclei.

Calculation of Energy Dependent Neutron Correction Coefficient Ratios of Natural Rhodium in Energy Region from 0.003 to 100 eV

Lee, Sam-Yol The Korean Society of Radiology 2008 한국방사선학회 논문지 Vol.2 No.3

In the neutron capture experiment and calculation, the neutron absorption and scattering are very important. Especially these effects are conspicuous in the resonance energy region and below the thermal energy region. In the present study, we obtained energy dependent neutron absorption ratios of natural rhodium in energy region from 0.003 to 100 eV by MCNP-4B Code. The coefficients for neutron absorption was calculated for several types of thickness. In the lower energy region, neutron absorption is larger than higher region, because of large capture cross section (1/v). Furthermore it seems very different neutron absorption in the large resonance energy region. These results are very useful to decide the thickness of sample and shielding materials.

Measurement of Neutron Capture Gamma-ray Spectrum of Natural Gold in the keV Energy Region

Lee, Jae-Hong,Lee, Sam-Yol,Lee, Sang-Bock,Lee, Jun-Haeng,Jin, Gye-Hwan The Korean Society of Radiology 2007 한국방사선학회 논문지 Vol.1 No.1

keV-neutron capture gamma-ray spectrum of $^{197}Au$(natural gold) sample have been measured in neutron energy range from 10 to 90 keV using the 3-MV pelletron accelerator of the Research Laboratory for Nuclear Reactors at the Tokyo Institute of Technology. Pulsed keV neutrons were produced from the $^7Li(p,n)^7Be$ reaction by bombarding on the $^7Li$ target with the 1.5-ns bunched proton beam. The incident neutron spectrum on the Au sample was measured by a $^6Li$-glass scintillation detector and TOF method. Capture gamma-rays from Au sample were measured by anti-Compton NaI(TI) spectrometer. Five average neutron energy regions were selected to obtain the neutron capture spectrum. Several gamma-ray peaks in the spectrum were found in the present experiment. 동경공업대학교의 3MV 펠레트론가속기를 사용하여 10에서 90keV 영역에 대하여 $^{197}Au$의 중성자포획 스펙트럼을 측정하였다. 중성자 펄스빔은 $^7Li(p,n)^7Be$반응을 통하여 발생되었다. 사용되어진 양성자 빔의 폭은 1.5-ns였다. 금 시료에 입사된 중성자의 에너지 스펙트럼은 $^6Li$-glass 섬광검출기의 중성자 비행시간법을 사용하여 측정하였다. 금 시료의 중성자포획에 의해서 발생된 감마선은 anti-Compton NaI(TI) 검출장비를 사용하여 측정되었다. 본 연구에서는 5개의 중성자 에너지 역영을 선택했고, 각각의 에너지영역에서 얻어진 감마선파고스펙트럼을 표시하였다. 본 연구에서 얻어진 스펙트럼은 처음으로 얻어진 결과이며, 중성자 결합에너지부근에 몇 개의 천이 피크가 보인다.

Resonance Integral of Neptunium(²³⁷Np) from Energy Dependent Differential Neutron Capture Cross-Section by Using the Linac TOF Method and C₆D₆ Scintillation Spectrometer

Lee, Sam-Yol The Korean Society of Radiology 2011 한국방사선학회 논문지 Vol.5 No.4

$^{237}Np$ is very important material in the fission products of nuclear reactors. Resonance integral(RI) tests of this material is necessary to check between the experiments and the evaluated data. Such feedback to the evaluated data is very important to correct data and improve of codes. The RI for the $^{237}Np(n,{\gamma})^{238}Np$ reaction were measured by using the 46-MeV electron linear accelerator (linac) at the Research Reactor Institute, Kyoto University (KURRI). The measurement was performed in the energy region from 0.005 eV and 10 keV. RI obtained as 804.7 barns, compared with those of the evaluated data in JENDL-4.0 and Mughabghab.

Measurement of Energy Dependent Neutron Capture Cross Section of 99Tc

Lee Sam-Yol,Lee Sang-Bock,Lee Jun-Haeng,Lee Jeung-Min,Yoon Jung-Ran 한국콘텐츠학회 2004 한국콘텐츠학회 종합학술대회 논문집 Vol.2 No.2

The neutron capture cross section of (99)^Tc has been measured relative to the (10)^B(n,g) standard cross section by the neutron time-of-flight(TOF) method in the energy range of 0.007 eV to 47keV using a 46-MeV electron linear accelerator(linac) at the Research Reactor Institute, Kyoto University(KURRI). In order to experimentally prove the result obtained, the supplementary cross section measurement has been made from 0.3 eV to 1 keV using the Kyoto University Lead slowing-down Spectrometer(KULS) coupling to the linac. The relative measurement by the TOF method has been normalized to the reference value(20.01 b) at 0.0253 eV and the KULS measurement to that by the TOF method.<br/> The existing experimental data and the evaluated capture cross sections in ENDF/B-VI, JENDL-3.2, and JEF-2.2 have been compared with the current measurements by the linac TOF and the KULS experiments. The energy dependency of the KULS data is close to that of the TOF data which are energy-broadened by the resolution function of the KULS.

Estimation of Neutron Absorption Ratio of Energy Dependent Function for $^{157}Gd$ in Energy Region from 0.003 to 100 eV by MCNP-4B Code

Lee, Sam-Yol The Korean Society of Radiology 2009 한국방사선학회 논문지 Vol.3 No.3

Gd-157 material has very large neutron capture cross section in the thermal region. So it is very useful to shield material for thermal neutrons. Futhermore, in the neutron capture experiment and calculation, the neutron absorption and scattering are very important. Especially these effects are conspicuous in the resonance energy region and below the thermal energy region. In the case of very narrow resonance, the effect of scattering is to be more considerable factor. In the present study, we obtained energy dependent neutron absorption ratios of natural indium in energy region from 0.003 to 100 keV by MCNP-4B Code. The coefficients for neutron absorption was calculated for circular type and 1 mm thickness. In the lower energy region, neutron absorption is larger than higher region, because of large capture cross section (1/v). Furthermore it seems very different neutron absorption in the large resonance energy region. These results are very useful to decide the thickness of sample and shielding materials.

Measurement of Branching Ratio for broad 27-keV Resonance of $^{19}F(n,g)^{20}F$ Reaction by using Time-of-flight Method with Anti-Compton NaI(Tl) Spectrometer

Lee, Sam-Yol The Korean Society of Radiology 2008 한국방사선학회 논문지 Vol.2 No.1

The neutron capture spectrum for the light nuclide was very useful to study the nuclear structure. In the present study, the capture gamma-ray from the 27-keV resonance of $^{19}F(n,g)^{20}F$ reaction were measured with an anti-Compton NaI(Tl) spectrometer and the 3-MV Pelletron accelerator of the Research Laboratory for Nuclear Reactors at the Tokyo institute of technology. A neutron Time-of-Flight method was adopted with a 1.5 ns pulsed neutron source by the $^7Li(p,n)^7Be$ reaction. In the present experiment, a Teflon(($CF_2$)n) sample was used The sample was disk with a diameter of 90mm. The thickness of sample was determined so that reasonable counting rates could be obtained and the correction was not so large for the self-shielding and multiple scattering of neutrons in the sample, and was 5mm. The primary gamma-ray transitions were compared with previous measurement of Kenny.