• Nuclear Engineering and Technology
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• v.4 no.2
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• pp.116-131
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• 1972

A fast neutron time-of-flight spectrometer has been constructed with suitable choice of target thickness and proton bombarding energy in Li$^{7}$ (p, n) Be$^{7}$ nuclear reaction for a continuous keV spectrum of neutrons at 0 degree in 1-nsec pulse from a Van do Graaff and a time-pick-up fast neutron detector assembled with a 5 mm-thick 92% enriched B$^{10}$ slab and four heavily shielded 4＂$\times$3＂ NaI scintillation detectors. Energy resolution of this spectrometer is better than 0.3% at 50 keV and the signal-to-background ratio is also improved. Total cross section measurements of several separated single isotopes have been carried out with this spectrometer and analyzed by Rmaxtrix multi-level computer code. The spin values and resonance parameters of each individual resonances are given.

• Proceedings of the Korean Vacuum Society Conference
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• 2015.08a
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• pp.100.1-100.1
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• 2015

중이온가속기에서 잔류기체 분자와 가속 이온의 충돌이 발생하면 이온빔 전류의 손실을 야기하는 직접적인 효과 외에 잔류 기체분자 중에서 전리된 이온들이 반발력에 의해 용기 벽에 부딪힐 때 표면에 흡착되어 있던 기체분자들을 충격탈리(stimulated desorption)시킨다. 더 심각한 경우는 산란된 고속 이온이 용기 벽과 충돌하면서 핵반응을 일으켜 방사화 시키거나 벽에서 다량의 기체를 방출시키는 것이다. 최악의 경우에는 고속이온의 에너지에 의해 용기벽이나 부품들이 열적인 손상을 입을 수도 있다. 현재 설계 및 연구개발이 진행중인 기초과학원(IBS) RISP (Rare Isotope Science Project)의 RAON 중이온가속기는 입사기에서 실험영역까지 각 부분의 진공도 조건이 일반적으로 10-8~10-9 mbar 대에 있어서 이온빔 전류의 손실이나 전리 이온들에 의한 충격탈리는 무시할 수도 있지만 고속이온의 기체방출 수율이 ~104 정도로 높은 것을 감안할 때 고속이온의 충격탈리에 의한 압력 증가가 감내할 수준인지 검토할 필요가 있다. 압력증가는 추가적인 손실을 유발하고 이것은 다시 압력을 상승시키는 진공 불안정성(vacuum instability)을 야기할 수 있다는 축면에서 조심하는 것이 좋다고 판단된다. 고속 중이온과 잔류기체 분자와의 충돌에서 이온이 손실되는 반응에는 쿨롬(coulomb) 산란과 전하교환(charge exchange)이 있는데 전자는 후자에 비해 일반적으로 1/10000 가까이 낮아서 무시할 수 있고, 전자 포획(electron capture) 또는 전자 손실(electron loss, 이온의 전리에 해당)로 대별되는 전하교환 반응이 이온 손실을 주도하는 것으로 알려져 있다. 이 연구에서는 다양한 전하교환 반응 단면적을 아우르는 비례칙(scaling law)을 사용하여 대표적인 중이온인 U33+ 및 U79+의 손실 및 잔류 기체의 전리율을 계산하고 충격탈리에 의한 표면방출 및 압력상승을 일차적으로 고려하여 진공도 조건의 타당성을 입증하려고 한다.

• Journal of Radiation Protection and Research
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• v.1 no.1
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• pp.1-9
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• 1976

A suggestion has been made for neutron dosimetric techniques using activation and threshold detectors in criticality accidents. Neutron dosimetrical parameters, namely, the fission spectrum-averaged cross-sections of some threshold reactions and fluence-to-dose conversion factors have been calculated by the use of an electronic computer. It appears that detectors having comparatively high threshold energy give more fine information on spectral deformation in criticality accidents, while detectors with low threshold energy are of usefulness for measuring fast neutron fluence regardless of fissioning types. Unexpectedly it is found that the fission spectrum-averaged cross sections of the $^{32}S(n,\;p)^{32}P$ reaction is not sensitive to analytical forms of fission neutron spectrum: the modified Cran-berg and Maxwellian forms. In addition, the fluence-to-dose conversion factors seem to be insensitive to both spectral functions and fissioning types.

• Transactions of the Korean Society of Mechanical Engineers
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• v.14 no.1
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• pp.112-118
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• 1990

Catastrophic fracture cannot be avoided after cracks(initiated from pre-existing defects) propagate rapidly with speeds comparable to a sound wave velocity of the materials. Preventing catastropic failure, crack arrest fracture toughness defined from dynamic(or kinetic) fracture mechanics point of view has been introduced in determining accurate and/or proper crack arrest fracture toughness of a material. For the past decades, many studies have been carried out to render proper theoretical and experimental backgrounds on the use of the static plain strain crack arrest fracture toughness, $K_{1a}$ (which seems to be a material property). $K_{1a}$ has been used to predict the performance of thick walled structures and has been considered as a measure of the ability of a material to stop a fast running crack. Determination of such a material property is of prime importance to the nuclear reactor pressure vessel and bridge materials industries. However, standards procedures for measuring toughness associated with fast running cracks are yet to exist. This study intends to give insight on the determination of the crack arrest fracture toughness of materials such as polymethylmethacrylate(PMMA), SM45C-steel, and A1 7075-T6. The effects of crack jump lengths and fast crack initiation stress intensity factor on the determination of $K_{1a}$ have been experimentally observed.erved.

• Proceedings of the Korean Society of Medical Physics Conference
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• 2004.11a
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• pp.69-71
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• 2004

The proton therapy of radiation therapy methods using Bragg Peak which is proton beam's characteristic dose distribution can give a normal tissue lower dose than cancer, comparing with the former existing radiation therapy methods. For exact treatment and patient' safety, we need to know proton beam's position in body, but a proton beam completely stops at treatment region and proton beam's range is uncertainly made by the variety of organs having each different density, so we aren't able to find a proton beam' position by suitable methods yet. With Monte Carlo Computing Method, as a result that we had simulated prompt gamma detection system using correlation of proton beam's absorbed dose distribution about water and prompt gamma distribution by nuclear interaction occurred by collisions of proton and water's hydrogen atoms, we could confirm that a proton beam's position was able to detect by using simulated prompt gamma detection system in body on the real-time

• Analytical Science and Technology
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• v.6 no.5
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• pp.501-508
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• 1993

In n/${\gamma}$ mixed field of $^{241}Am-Be$(${\alpha}$, n) neutron source, we seperated the neutron component from gamma ray component. At the center of the detector, $^6Li$ was doped on the cerium activated glass plate for $^6Li$(${\alpha}$, n)T nuclear reaction. The time differences of the light following excitations by different scintillators, BC501($C_8H_{10}$) and cerium, and by the same scintillator for different radiations as neutrons and gamma-rays are used to apply the methods of PSD(Pulse Shape Discriminator) and CFD(Constant Fraction Discriminator). The figure of merit of $^6Li$ fast neutron spectrometer is estimated as 1.36.

• Journal of Radiation Protection and Research
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• v.11 no.2
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• pp.139-145
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• 1986

An improved mothod of assessing fuel status by analyzsis of the fission product in the reactor coolant system is proposed. The release mechanism of specific fission products is established for determination of the coefficients in the equations which relate the radioactivities with the amount of defected fuel. Knock-out and migration models are employed in the formulation of the release mechanism. The influence of the tramp uranium is quantified. Sample calculations were made for KNU 1 reactor system using the I-131 and I-133 concentrations in the primary coolant. The estimated number of defected fuel pins in the third and sixth cycles appeared to be $9.34{\pm}1.13\;and\;0.294{\pm}0.092$, respectively.

• Proceedings of the Korean Vacuum Society Conference
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• 2012.02a
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• pp.173-173
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• 2012

사이클로트론은 암진단에 사용되는 방사성동위원소를 생산하기 위한 중요한 입자 가속장치이다. 현재 핵의학 의료진단에 필요한 방사성동위원소를 제공하기 위해 세계적으로 사이클로트론의 활용도가 점점 증가하고 있다. 한국원자력의학원에 설치된 MC50 (양성자 최대 가속에너지 50 MeV, 60 uA)과 C30 (양성자 최대 에너지 30 MeV, 250 uA) 사이클로트론은 생명의학, 반도체 검출기, 핵자료 데이터, 방사성동위원소 개발 등 다양한 분야의 연구를 지원하고 있다. MC50 사이클로트론은 수소 입자를 포함하여 중양자, 알파 입자를 가속할 수 있으며 중성자 빔을 인출 할 수 있다. 수소 음이온 또는 양이온을 가속 할 수 있으며 표적에는 고에너지의 양이온이 조사되며, 핵반응을 통해 방사성동위원소가 생성된다. 양성자 빔을 이용하여 암세포를 사멸 시키는 치료법, 돌연변이로 새로운 종의 개발 등 다양한 응용성이 있다. 하전입자를 가속하는 사이클로트론의 주요 구성요소는 (1) 진공시스템, (2) 전자석 시스템, (3) 고주파 시스템, (4) 이온원 (5) 빔 인출장치 (6) 빔전환 장치 (수직에서 수평 방향으로 전환), (7) 빔 집속 및 진단 장치 등 이다. 본 발표에서는 85년부터 운영한 MC50 사이클로트론과 02년부터 가동된 사이클로트론의 운영 현황 및 다양한 응용분야와 향후 RI 빔 인출을 위한 계획을 소개하고자 한다.

• Journal of the Korea Institute of Information and Communication Engineering
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• v.18 no.6
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• pp.1462-1468
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• 2014

Xe gas is moved to target from GPM. It is used to feasible nuclear reaction from proton of 30MeV cyclotron being investigated by the Xe-124 gas target system. This system is divided into four parts. The hardware system was constructed by solidworks 3-D CAD and Helium supply is to cool the Havor foil. The Cooling water has the job of cooling down the temperature when Xe gas is being investigated in the target. Temperature and pressure gauges are attached to be checked easily. GPM has the part that prepares to transport Xe gas. There are storage vessel that stores Xe gas, the cold trap that filters humidity and impurity and lastly storage vessel that temporarily stores Xe gas. HCS using the helium is to clean and cool for each part. These parts are configured with SIEMENS PLC and PcVue monitoring program for more comfortable and easy maintenance.

• Analytical Science and Technology
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• v.17 no.1
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• pp.8-15
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• 2004

The detection efficiencies of the several solid track detectors were investigated for the determination of boron content in aqueous solution by using the alpha muti-Radioisotope(RI) source. Polycarbonate (Lexan and CR-39) and cellulose nitrate (CN-85 and LR-115) were selected as materials for alpha track detection of boron. Alpha muti-RI source, uranium metal particles and boron standard solution were used for alpha emission. In this study, four solid track detectors(CN-85, LR-115, Lexan and CR-39) were characterized under various etching conditions as well as neutron irradiation conditions. As a result, the CN-85 was turned out to be best to provide good efficiency among the four detectors. The selected solid track detector was utilized for the determination of trace amount of boron in aqueous sample and its results were discussed in the text.