• 한국재료학회:학술대회논문집
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• 한국재료학회 2011년도 춘계학술발표대회
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• pp.15-15
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• 2011

As you know, boron compounds, borax ($Na_2B_4O_5(OH)_4{\cdot}8H_2O$) etc. were known thousands of years ago. As for natural boron, it has two naturally occurring and stable isotopes, boron 11 ($^{11}B$) and boron 10 ($^{10}B$). The neutron absorption $^{10}B$ is included about 19~20% with 80~81% $^{11}B$. Boron is similar to carbon in its capability to form stable covalently bonded molecular networks. The mass difference results in a wide range of ${\beta}$ values between the $^{11}B$ and $^{10}B$. The $^{10}B$ isotope, stable with 5 neutrons is excellent at capturing thermal neutrons. For example, it is possible to decrease a thermal neutron required for the nuclear reaction of uranium 235 ($^{235}U$). If $^{10}B$ absorbs a neutron ($^1n$), it will change to $^7Li+^1{\alpha}$ (${\alpha}$ ray, like $^4He$) with prompt ${\gamma}$ ray from $^{11}B$ $^{11}B$ (equation 1). $$^{10}B+^1n\;{\rightarrow}\;^{11}B\;{\rightarrow}\; prompt \;{\gamma}\;ray (478 keV), \;^7Li+4{\alpha}\;(4He)\;\;\;\;{\cdots}\; (1)$$ If about 1% boron is added to stainless steel, it is known that a neutron shielding effect will be 3 times the boron free steel. Enriched boron or $^{10}B$ is used in both radiation shielding and in boron neutron capture therapy. Then, $^{10}B$ is used for reactivity control and in emergency shutdown systems in nuclear reactors. Furthermore, boron carbide, $B_4C$, is used as the charge of a nuclear fission reaction control rod material and neutron cover material for nuclear reactors. The $B_4C$ powder of natural B composition is used as a charge of a control material of a boiling water reactor (BWR) which occupies commercial power reactors in nuclear power generation. The $B_4C$ sintered body which adjusted $^{10}B$ concentration is used as a charge of a control material of the fast breeder reactor (FBR) currently developed aiming at establishment of a nuclear fuel cycle. In this study for new boron compound, silicon boride ceramics for capturing thermal neutrons, preparation and characterization of both silicon tetraboride ($SiB_4$) and silicon hexaboride ($SiB_6$) and ceramics produced by sintering were investigated in order to determine the suitability of this material for nuclear power generation. The relative density increased with increasing sintering temperature. With a sintering temperature of 1,923 K, a sintered body having a relative density of more than 99% was obtained. The Vickers hardness increased with increasing sintering temperature. The best result was a Vickers hardness of 28 GPa for the $SiB_6$ sintered at 1,923K for 1 h. The high temperature Vickers hardness of the $SiB_6$ sintered body changed from 28 to 12 GPa in the temperature range of room temperature to 1,273 K. The thermal conductivity of the SiB6 sintered body changed from 9.1 to 2.4 W/mK in the range of room temperature to 1,273 K.

• 지구물리와물리탐사
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• 제22권3호
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• pp.149-159
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• 2019

암석구성성분검층(중성자-감마스펙트로스코피검층)은 중성자선원의 비탄성산란과 중성자포획 작용으로부터 생성되는 감마선을 측정하여 지층의 원위치 광물조성을 추정할 수 있는 기술이다. 일반적으로 지층의 광물조성 평가는 코어에 대한 X선 회절법, X선 형광분석법 등의 실내 시험자료를 주로 이용하고 있으나 이는 조사 구간의 극히 일부분에 대한 결과이며 특히, 유체의 유동 경로 구간은 주로 파쇄대 및 사질층인데 이 구간들의 코어 회수율이 불량하여 조사 구간 전체에 대한 광물조성 평가는 한계가 있다. 따라서 시추공 전 구간에 대한 원위치 광물조성 추정 기술개발은 지중환경 평가에 중요한 역할을 할 수 있다. 이 기술은 전통, 비전통 저류층 평가를 중심으로 최근까지 장비 개발 및 관련 연구가 활발히 진행되고 있는 분야이지만 몇 개 서비스회사의 독점기술로 자세한 정보 미공개, 다양한 지층 및 인공모형을 이용한 화학-광물학 데이터베이스 구축 문제 등으로 국내 연구에 직접적으로 적용하기에는 어려움이 있었다. 이 해설논문에서는 암석구성성분검층의 기본원리, 시스템 구성, 교정시설, 국외 기 개발된 검층시스템 분석 및 연구개발 동향 등을 통해 해당 기술을 소개하고, 국내 시스템 제작을 위한 기술 적용 방안을 검토하였다.

• Nuclear Engineering and Technology
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• 제56권6호
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• pp.2317-2323
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• 2024

Medical linear accelerators with an energy of 8 MV or higher are radiated owing to photonuclear reactions and neutron capture reactions. It is necessary to quantitatively evaluate the concentration of radioactive isotopes when replacing or disposing them. HPGe detectors are commonly used to identify isotopes and measure radioactivity. However, because the detection efficiency is generally calibrated using a standard material with a density of 1.0 g/cm³, a self-absorption effect occurs if the density of the measured material is high. In this study, self-absorption correction factors were calculated for tungsten, lead, copper, and SUS-303, which are the main materials of medical linear accelerator head parts, for each gamma-ray energy using MCNP 6.2 code. The self-absorption effect was more pronounced as the energy of the emitted gamma rays decreased and the density of the measured materials increased. These correction factors were applied to the radioactivity measurements of the in-built and portable HPGe detectors. Furthermore, compared to the surface dose rate measured by the survey meter, the accuracy of the measurements of radioactivity improved by an average of 124.31 and 100.53 % for inbuilt and portable HPGe detectors, respectively. The results showed a good agreement, with an average difference of 3.70 and 5.24 %.

• 한국의학물리학회지:의학물리
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• 제18권2호
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• pp.87-92
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• 2007

최대출력 30 MW, 하나로(HANARO) 다목적 연구용 원자로의 접선 중성자공에 붕소중성자포획치료(Boron Neutron Capture Therapy, BNCT)를 위한 열중성자 조사장치가 개발되었다. BNCT 조사장치에서는 서로 다른 물리적 특성과 생물학적 효과비를 가진 여러 성분의 방사선이 방출되기 때문에 정확한 투여선량을 결정하기 위해서는 각 성분의 정량적 분석이 필수적이다. 따라서 본 연구에서는 방사화 분석, 열형광선량계 및 이온전리함 등 여러 유형의 검출기를 사용하여 BNCT 조사장치에서 방출되는 열중성자 및 감마선 혼합장의 선량 성분을 분리, 측정하였다. 선량측정은 물 속에 함유된 불순물과 중성자의 이차반응을 최소화하기 위해 증류수를 채운 물팬텀을 이용하였다. 그리고 측정 결과는 MCNP4B 전산계산의 결과와 상호 비교하였다. 측정 결과 열중성자속은 물팬텀 10 mm와 20 mm 깊이에서 각각 $1.02E9n/cm^2{\cdot}s$과 $6.07E8n/cm^2{\cdot}s$이었고, 고속중성자선량율은 10 mm 깊이에서 0.11 Gy/hr로 미세하였다. 감마선량률은 물팬텀 20 mm 깊이에서 5.10 Gy/hr로 나타났다. 측정된 중성자와 감마선량값은 MCNP의 결과와 5% 이내로 잘 일치하였고, 열중성자속은 14%의 비교오차를 나타내었다. 이러한 결과들은 중성자 검출의 난이도를 고려할 때 충분히 신뢰할 수 있는 수준이라 판단되며, BNCT 임상 연구를 위한 선량평가 자료로 활용할 수 있을 것으로 사료된다.

• Nuclear Engineering and Technology
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• 제4권4호
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• pp.340-344
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• 1972

$^{79}$ Br, $^{80}$ Se, $^{103}$ Rh, $^{115}$ In 및 $^{133}$ Cs의 열중성자 포획시 혈성되는 이성체쌍의 비와 $^{79}$ Br, $^{80}$ Se 및 $^{l33}$Cs의 Epi-Cd 중성자 포획시 형성되는 이성체 쌍의 비를 측정하였다. 동 이성체비는 중성자 조사후 ${\gamma}$-선 분광분석법으로 얻은 붕괴곡선을 분석하여 측정하였다. 계측효율곡선은 전체불확실율이 악 1%인 표준선원을 사용하여 결정하였다. $\sigma$ high spin/($\sigma$ high spin+$\sigma$ low spin)으로 나타낸 열중성자로 생성된 $^{80, 80m}$Br, $^{81,81m}$Se, $^{014, 104m}$Rh, $^{116,116m}$In 및 $^{134, 134m}$Cs 쌍들의 이성체비는 각각 0.21$\pm$0.01, 0.14$\pm$0.02, 0.12$\pm$0.02, 0.69$\pm$0.07 및 0.058$\pm$0.004 이었다. Epi-Cd 중성자에 의해서 생성된 $^{80, 80m}$Br, $^{81,81m}$Se, 및 $^{134, 134m}$Cs 쌍의 이성체 비는 각각 0.19$\pm$0.02, 0.29$\pm$0.02 및 0,74$\pm$0,011 이었다. 실험적으로 얻은 본값을 통계적 모델로부터 얻은 이론치와 비교하여 본 결과 일반적인 일치를 보였다.다.

• 대한핵의학회지
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• 제25권2호
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• pp.286-293
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• 1991

$^{123}I$, which is applied for the thyroid and other in vivo kinetic study, has a special role in life sciences. The 159 KeV $\gamma-ray$ from $^{123}I$ is almost ideally appropriate for the current imaging instrumentation. Its decay mode (electron capture) and short half-life (13.3 hr) reduced the burden of radiation dose to the patients, and its chemical property makes it easy to synthesize the labelling compounds. In this experiment, the production of $^{123}I$ via the nuclear reaction $^{124}Te(p,2n)^{123}I$ with 28 MeV protons was sutdied. $TeO_2$ is used as a target material, because it has good physical properties. The target was prepared with $TeO_2$ powder and was molten into a ellipsoidal cavity (a=14 mm, b=10 mm, $270.8mg/cm^2$ thick) of pure platinum. The irradiation was carried out in the external proton beam with incident energies range from 28 MeV to 22 MeV, and current was $30{\mu}A$. The loss of $TeO_2$ target was significantly reduced by using $4\pi-cooling$ system in irradiation. The dry distillation method was adopted for the separation of $^{123}I$ from irradiated target, and when it was kept 5 minutes at $780^{\circ}C$, its result was quantitative. The loss of the target material $(TeO_2)$ was below 0.2% for each production run and $^{123}I$ from the dry distillation apparatus was captured with 0.01 N NaOH in $Na^{123}I$ form, then the pH of the solution was adjusted to $7.5\sim9.0$ with HC1/NaOH. The $Na^{123}I$ solution was passed through $0.2{\mu}m$ membrane filter, and sterilized under high pressure and temperature for 30 minutes. The production of $^{123}I$ is acceptable for clinical application based on the quality of USP XXI.