• 대한방사선방어학회:학술대회논문집
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• 2009.04a
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• pp.218-219
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• 2009

• Proceedings of the KIEE Conference
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• 2005.07c
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• pp.2160-2162
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• 2005

중성자 발생을 위한 구형 집속빔 핵융합 장치 방전의 실험적 결과들이 제시되었다. 실험 장치는 직경 22cm, 높이 20cm의 진공용기 안에 동심원적으로 위치한 구형 양극과 grid 음극으로 구성된다. 진공용기에 아르곤 기체를 주입하고, grid 음극에 펄스 전압을 인가하여 방전을 발생시켰다. 다양한 grid 음극에 대한 방전의 실험적 결과들이 전자적, 광학적으로 측정되었다.

• Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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• v.2 no.2
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• pp.97-104
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• 2004

Neutron induced prompt gamma-ray spectroscopy(NIPS) system measures the prompt gamma-ray emitting by the interaction of a neutron with various materials. This system will be of great benefit to scientists worldwide, since it provides the non-destructive measurement of many element in either solid or liquid wastes. In this study, the full-energy-peak (FEP) efficiency calibration for a HPGe detector was constructed in the ${\gamma}$-ray energy range from 80 keV to 8 MeV, using $^{l33}$Ba and >TEX>$^{152}Eu$ RI sources and $ ^{35}Cl(n, ${\gamma}$)^{36}Cl$ thermal neutron captured reaction. The FEP efficiency curve for the higher energies using the $^{35}Cl(n, ${\gamma}$)^{36}Cl$ reaction was normalized with the curve obtained from the RI sources, since the accurate activity of its prompt ${\gamma}$-ray is unknown. The average thermal neutron flux was theoretically calculated using the FEP efficiency curve for the KCl standard solutions. The NIPS system equipped with a ${\gamma}$-${\gamma}$ coincidence setup with two n-type coaxial HPGe detectors was considered in order to reduce the interfering ${\gamma}$-ray background. The FEP efficiency curve for the ${\gamma}$-${\gamma}$ coincidence system was also obtained for full energy range. The performance of the normal and coincidence NIPS system was tested by comparing signal-to-noise ratio in each mode using the reference sample.e.

• Korean Journal of Materials Research
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• v.8 no.11
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• pp.1020-1025
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• 1998

Irradiation-induced changes in mechanical properties and magnetic parameters were measured and compared to explore possible correlations for Mn-Mo-Ni low alloy steel surveillance specimens which were irradiated to a neutron fluence of $2.3\times10^{19}n/cm^2$(E>1.0MeV) in a typical pressurized water reactor environment at about $288^{\circ}C$. For mechanical property parameters, microvickers hardness, tensile and Charpy impact test were performed and Barkhausen noise amplitude, coercivity, remanence, maximum induction were measured for magnetic parameters. respectively. Results of mechanical property measurements showed an increase in yield and tensile strength, microvickers hardness. 41J indexed $RT_{NDT}$ and a decrease in upper shelf energy irrespective of base and weld metals. However, in the case of tensile properties, the changes in weld metal were negligible compared to the base metal. In the case of magnetic measurements, it is found that magnetic remanence, BN amplitude. BN energy have dropped significantly but coercivity(H,) has increased rapidly after irradiation. In this study. the measurements conducted on surveillance specimens of Mn-Mo-Ni low alloy steel showed that there were strong correlations between mechanical properties and magnetic properties.

• Korean Journal of Materials Research
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• v.9 no.12
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• pp.1240-1244
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• 1999

In order to assess the effects on the magnetic properties due to the defect in the material irradiated by fast neutron ranging $10^0-10^{18}n/cm^2$, the magnetic properties such as maximum magnetic induction, coercivity, remanence, Barkhausen Noise Amplitude(BNA), Barkhausen Noise Energy(BNE) and hardness were measured. It is shown that the magnetic properties and hardness do not change by the fast neutron irradiation under $10^{17}n/cm^2$. Therefore, in this experiment, it is understood that the magnetic properties decrease by the increase of hardness. This measurement method can be used to evaluate the neutron irradiation embrittlement nondestructively since the magnetic properties and hardness do change by the neutron irradiation over $10^{17}n/cm^2$ consistently.

• Journal of Radiation Protection and Research
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• v.29 no.1
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• pp.17-23
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• 2004

In order to save time and money needed in the purchase commonly used gamma-ray standard sources, a new radioactive standard source was manufactured by the neutron activation of some regent in the research reactor HANARO. The source was manufactured with an aqueous solution by mixing and dissolving the irradiated reagents. The manufactured source was compared with a commercial standard source. It was confirmed that it could be used as an efficiency calibration source. Also, in order to compare the variation of efficiency due to the volume difference for various containers used in radioactivity assay, the efficiency variation as a function of sample volume was investigated.

• Journal of the Korea Academia-Industrial cooperation Society
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• v.15 no.6
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• pp.3734-3740
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• 2014

The aim of this study was provide basic information and establish the criteria in radiation therapy planning by measuring the absorbed neutron dose of normal tissues and lesions according to the number of portals. From September 2013 to January 2014, 20 patients who were diagnosed with prostate cancer and were previously treated with radiation therapy were replanned retrospectively to measure the absorbed neutron dose distribution according to the number of portals. The absorbed neutron dose was measured in each of the 5, 7 and 9 portals using a 15 MV energy, which meant a therapeutic dose of 220 cGy. The optical stimulation luminescence dosimeter was separated by 20cm and 60cm away from the center of the field of view. As a result, the average radiation dose in the abdomen appeared to have a positive relationship with the number of portals, which was statistically significant (p<.05). The average radiation dose was $4.34{\pm}1.08$. The average radiation dose in the thyroid was $2.71{\pm}.37$. Although it showed a positive relationship with the number of portals, it did not have statistical significance. The number of portals and the neutron dose depending on the position showed a significant positive relationship, particularly in the abdomen. As a result of linear regression analysis, as the number of the portal increased in steps, the average volume of the neutrons increased significantly (0.416 times). In conclusion, efficient selection of the number of portals is needed considering the difference in the absorbed neutron dose in the normal tissues depending on the number of the portals.

• Journal of Radiation Protection and Research
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• v.17 no.2
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• pp.61-70
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• 1992

Photon, neutron and beta radiation fields were measured at PWR plants which are the representative types of nuclear power plant operated in Korea. The photon energy spectra were measured at locations in the auxiliary building during operation period and in the containment vessel(C/V) during shutdown period using a portable gamma spectrometer with a HPGe detector. The distribution of average energy was found to range from 440 to 780 keV in the C/V and from 280 keV to 760 keV in the auxiliary building, respectively. The average neutron energy measured at the five locations around the operation deck in the C/V in operation using a BMSS (Bonner Multi-Sphere Spectrometer) ranged from 20 keV to 210 keV. A computer code, BUNKI was used to unfold the spectrum. The beta energy spectra in the C/V and in the auxiliary building in annual outage were determined using 14 smear samples taken from the highly contaminated areas. The analysis showed that the representative corrosion product, $^{60}Co$ made main contribution to the beta energy field.

• Proceedings of the Korean Nuclear Society Conference
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• 1997.05a
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• pp.557-562
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• 1997

노심용융물의 노내 자연 냉각 현상은 TMI-2 사고 이래로 실험과 해석 분야에서 많은 연구가 이루어지고 있으나, 아직까지는 이에 대한 명확한 규명이 이루어지지 않은 상태이다. 원자로 용기 냉각 Mechanism 중에서 노심용융물이 원자로 용기 하부 반구내로 재배치되어 하부 반구 내벽과 접촉할 때 용융물과 하부 반구 내벽 사이에 생길 수 있는 작은 간극으로 냉각수가 침투되어 노심용융물의 냉각이 이루어질 수 있다는 가정이 유력하게 제기되고 있다 본 논문에서는 노심용융물과 원자로 용기 하부 반구 사이의 간극을 통한 노심용융물의 냉각 특성을 규명하는 SONATA-IV실험 연구와 연계하여 이상 유동이 존재하는 고온 표면에서의 미세한 간극을 측정할 수 있는 방법의 검토 및 시편을 이용한 실험을 통하여 가장 적합한 간극측정기법을 도출하였다 간극 측정 기법으로는 중성자 래디오그라피, X 선 후방산란 단층기법 그리고 초음파 펄스 반사 탐상법을 검토하였으며, 시편 측정 실험결과 실시간 간극 측정방법으로는 초음파 펄스 반사 탐상법이 가장 적합한 것으로 나타났다.

• Journal of Radiation Protection and Research
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• v.18 no.2
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• pp.71-79
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• 1993

Form the pure Maxwellian distribution(kT= 1.42MeV), the effects upon calibration factors of encapsulating a $^{252}Cf$ spontaneous fission neutron source were investigated to establish a standard neutron field in the Secondary Standard Dosimetry Laboratory at Korea Atomic Energy Research Institute(KAERI). A Monte Carlo code MCNP was used in simulating the encapsulation SR-Cf-100 and SR-Cf-1273 to be real conditions. The anisotropy(FI) and fluence-to-dose equivalents conversion factors$(H/{\Phi})$ were evaluated and compared with other results. As the results, the FI was determined to be 1.061 at ${\theta}=90^{\circ}$ with ${\pm}0.2%$ statistical error and the $(H/{\Phi})$ was evaluated to be $333.9 [pSv\;cm^2]\;with\;{\pm}0.5%$ statistical error, which is lower by 1.8% than that recommended by the ISO 8529. This means physically that the neutron spectrum of the unmoderated $^{252}Cf$ source in KAERI is a little more softened than that by the ISO.