• 대한방사선방어학회:학술대회논문집
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• 2010.04a
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• pp.74-75
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• 2010

• Journal of Radiation Protection and Research
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• v.25 no.2
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• pp.67-73
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• 2000

The effects of combined irradiation of neutrons and ${\gamma}$-rays were analysed by means of Tradescantia stamen hair (TSH) assay. Potted plants were irradiated with $0{\sim}2$ Gy of ${\gamma}$-rays. For the combined treatments, the plants were irradiated with neutrons from $^{252}Cf$ 24 hours before or after ${\gamma}$-irradiation. The slopes of dose-response curves were 5.98, 6.17 and 7.48, in ${\gamma}$-rays, ${\gamma}$-rays+neutrons, and neutrons+${\gamma}$ -rays irradiated groups, respectively. The biological efficacy of radiations in the induction of pink mutations increased by 25% in neutrons+${\gamma}$-rays irradiated group, while it increased by 12% in ${\gamma}$-rays+neutrons irradiated group. The combined irradiation with two kinds of radiations results in the different efficacy of radiation depending on the order of irradiations, which is of great importance in the related fields such as sterilization and radiotherapy.

• Journal of radiological science and technology
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• v.26 no.3
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• pp.51-57
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• 2003

Mitigation of fast neutron irradiation damage on reactor vessel and improvement of mechanical integrity are desired for the successful plant life-time extension. In this study, the performance of metallic hydride for this application is reviewed and compared. First, selected prospective metallic hydrides are evaluated by MCNP code and put into the attenuation test using Cf-252 neutron source. Since for the reactor application high moderation and reflection with no absorption are favored, Z factor is introduced for the evaluation. According to the Z value estimation $ZrD_2$ and $TiD_2$ are turned out to be the most favorable fast neutron shielding materials. More thorough evaluation by computer simulation and experimentally, will be followed.

• Journal of Radiation Protection and Research
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• v.38 no.1
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• pp.44-51
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• 2013

ICRP recommended that cosmic ray exposure to the pilot and cabin crew would be considered as an occupational exposure due to their relatively high exposure. Since 2012 with the Act No. 10908 (Natural radiation management), the guideline of cosmic ray exposure to the pilot was established in Korea. The applicability of the solid-state nuclear track detector for personal dose assessment of pilot and cabin crew was evaluated. Dose linearity and angle dependence of dosimeters to the neutron were evaluated by $^{252}Cf$ neutron emitting source. The track density has a good agreement with the dose ($r^2$=0.99) and highly dependent on the degree of an angular of the dosimeter to the neutron source. In addition, the dosimeters (SSNTD) were exposed to cosmic ray in an aircraft during its cruising for more than two months in collaboration with Airline Pilots Association of Korea. Although the correlation between the track density from aircraft cruising altitude and expected neutron dose is low, however RSNS dosimeter could be used for personal neutron dosimeter. For application of RSNS as a personal dosimeter for pilot and cabin crew, additional studies are required.

• 대한방사선방어학회:학술대회논문집
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• 2011.11a
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• pp.252-253
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• 2011

• 대한방사선방어학회:학술대회논문집
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• 2009.11a
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• pp.170-171
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• 2009

• 대한방사선방어학회:학술대회논문집
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• 2011.11a
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• pp.140-141
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• 2011

• Proceedings of the Korean Nuclear Society Conference
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• 1997.05b
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• pp.231-236
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• 1997

방사성물질의 수송 및 저장용기 등에 사용되는 실리콘고무계 및 수소 첨가된 비스페놀-A형 에폭시수지계 중성자 차폐재들의 인장강도, 압축강도, 비중, 무게, 수소함량 등에 방사선이 미치는 영향을 검토하였다. 방사선 조사선량의 증가에 따라 실리콘고무계 중성자 차폐재(KNS-101 및 102)들의 인장강도, 압축강도, 비중 등이 증가하는 경향을 나타내었으며, 차폐재의 무게는 거의 변화가 없었으나, 수소함량은 약간 감소하는 경향을 나타내었다. 또한 에폭시수지계 중성자 차폐재(KNS-201 및 202)들의 인장강도 및 압축강도는 0.1 MGy까지는 방사선 조사선량의 증가에 따라 증가하다가 0.1MGy 이상에서는 감소하는 경향을 나타내었으며, 조사선량의 증가에 따른 차폐재들의 비중, 무게 및 수소함량은 크게 변하지 않는 것으로 나타났다.

• Journal of the Korean Society of Radiology
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• v.7 no.3
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• pp.245-249
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• 2013

Neutron sources from photonuclear reaction with 46-MeV electron linear accelerator at Research Reactor Institute, Kyoto University used for resonance energy measurement of natural tantalum. BGO($Bi_4Ge_3O_{12}$) scintillation detectors used for measurement of the prompt gamma ray from the natural tantalum sample. The BGO spectrometer was composed geometrically as total energy absorption detector. The electric signal from the spectrometer was analyzed for TOF(Time-of-Flight) spectrum which is used identification of neutron capture resonance energy. In this study, the neutron energy region is from 1 to 200 eV, because of strong X-ray effect produced photonuclear reaction in Ta target, the measurement was performed to below 1 keV energy region. The resonance energy was compared with the evaluated values(ENDF/B-VI, Mughabghab). All of the resonances from 4.28 ~ 200 eV were seen in the present measurement except 144.3 eV resonance.

• Proceedings of the Korean Nuclear Society Conference
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• 1998.05a
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• pp.227-232
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• 1998

하나로 1차 배관에서 중성자를 측정하고 발생 원인을 분석하였으며, 이를 통하여 중성자 계측 계통을 이용하여 핵연료 파손을 감시할 수 있는 가능성을 검토하였다. 중성자 측정에는 BF$_3$비례 계수관을 이용하였고, 1차 배관의 주 방사선원인 N-16에 의한 감마선 펄스의 영향은 무시 할 정도로 작았다. 중성자의 발생 원인을 규명하기 위해 원자로 정지 전후에 중성자 계수율의 변화를 측정하였다. 편자로의 정상 운전시 1차 배관에서 발생되는 중성자는 물속의 중수소가 고에너지 감마선을 흡수하여 방출하는 광중성자와 핵연료의 표면 오염에 의해 발생된 지발 중성자라고 가정하여 원자로 정지 전후의 발생량 변화를 계산하였다. 계산 결과와 측정값을 비교하여 1차 배관 주변에서 측정된 중성자 가운데 지발 중성자가 약 70 %, N-16에 의한 광중성자가 약 30%임을 확인하였다. 핵연료의 표면 오염 정도로 발생하는 지발 중성자도 민감하게 측정되므로, 이러한 지발 중성자 계측법이 핵연료의 손상 여부를 알아낼 수 있는 유용한 방법임을 확인할 수 있었다.