• Proceedings of the Korean Radioactive Waste Society Conference
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• 2004.06a
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• pp.347-348
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• 2004

차세대관리 종합공정 실증시설의 핫셀 차폐벽은 중량콘크리트 재질로서 외벽의 두께는 90cm 이상으로 설계되었으며, 차폐벽의 모든 부위는 이와 동일한 차폐능을 확보하도록 하여야 한다. 그러나 핫셀 운영을 위하여 불가피하게 설치되는 여러 가지 부속 시설물들에 의하여 원래 계획한 핫셀 차폐벽의 차폐능 저하를 가져오게 되며, 이런 부속 시설물로는 차폐 출입문, 방사성 물질을 핫셀 내부로 반입하거나 반출하기 위한 수송용기 접합부, 소형물 투입구, 슬리브 및 매설관등이 있다.(중략)

• Proceedings of the Materials Research Society of Korea Conference
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• 2003.11a
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• pp.228-228
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• 2003

차세대관리 종합공정에서 취급되는 기준 방사선원은 경수로에서 배출된 우라늄-235 농축도 3.5 wt%, 연소도는 43 Gwd/tU 이며 냉각기간은 10년인 사용후핵연료이다. 사용후핵연료의 기준 사양과 차세대관리 종합공정의 특성에 따라 최대 1,385 TBq의 방사선원이 핫셀내에 존재하게 되며, 핫셀 차폐벽은 총 방사능량에 대한 차폐능을 가져야 한다. 최대 방사선원에 대한 핫셀 차폐벽의 중성자에 대한 차폐능을 평가하기 위하여, 본 연구에서는 ORIGEN-2 코드를 이용하여 사용후핵연료에서 발생하는 핵종 및 핵종량을 평가하였으며, 이 자료를 기초로 하여 중성자 선원항을 SOURCES코드를 이용하여 계산하였다.

• Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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• v.2 no.1
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• pp.1-11
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• 2004

The hot cell facility for research activities related to the lithium reduction of spent fuel, which is designed to permit safe handling of source materials with radioactivity levels up to 1,385 TBq, is planned to be built. To meet this goal, the facility is designed to keep gamma and neutron radiation lower than the recommended dose-rate in normally occupied areas. The calculations peformed with QAD-CGGP and MCNP-4C are used to evaluate the proposed engineering design concepts that would provide acceptable dose-rates during a normal operation in hot cell facility. The maximum effective gamma dose-rates on the surfaces of the facility at operation area and at service area calculated by QAD-CGGP are estimated to be $2.10{\times}10^{-3}, 2.97{\times}10^{-3} and 1.01{\times}10{-1}$ mSv/h, respectively. And those calculated by MCNP-4C are $1.60{\times}10^{-3}, 2.99{\times}10^{-3} and 7.88{\times}10^{-2}$ mSv/h, respectively, The dose-rates contributed by neutrons are one order of magnitude less than that of gamma sources. Therefore, it is confirmed that the radiological design for hot cell facility satisfies the Korean criterion of 0.01 mSv/h for the operation area and 0.15 mSv/h for the service (maintenance) area.

• Proceedings of the Korean Radioactive Waste Society Conference
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• 2003.11a
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• pp.584-589
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• 2003

The hot cell facility which is designed to permit safe handling of source materials with radioactivity levels up to 1,385 TBq, is planned to be built. To meet this goal, the facility is designed to keep gamma and neutron radiation lower than the recommended dose-rate in normally occupied areas. The calculations performed with QAD-CGGP and MCNP-4C are used to evaluate the proposed engineering design concepts that would provide acceptable dose-rates during a normal operation in hot cell facility. The maximum effective gamma dose-rates on the surfaces of the facility at operation area and at service area calculated by QAD-CGGP are estimated to be $2.10{\times}10^{-3}$, $2.97{\times}10^{-2}$ and $1.01{\times}10^{-1}$ mSv/h, respectively. And those calculated by MCNP-4C are $1.60{\times}10^{-3}$, $2.99{\times}10^{-3}$ and $7.88{\times}10^{-2}$ mSv/h, respectively The dose-rates contributed by neutrons are one order of magnitude less than that of gamma sources, and penetration and toboggan will be partly reinforced by lead shield.

• Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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• v.4 no.1
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• pp.77-85
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• 2006

A demonstration facility for an advanced spent fuel conditioning process (ACP) is under construction at KAERI. In this hotcell facility, the rear door is frequently used since all process equipment and materials are taken in and out only through the rear door. Therefore , both the structural safety and stability of the door are essentially required for the safety of ACP facility. In this paper, the finite element analysis has been performed to investigate the structural safety under the impact condition between the rear door and the door frame. Also the possibility of the rear door being tumbled over by the impact force or the inertia force under a sudden stop conditon has been evaluated. The analysis results demonstrate that the structural safety and stability of the rear door are sufficiently assured for both the impact and the accidential stop conditions.

• Proceedings of the Materials Research Society of Korea Conference
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• 2003.03a
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• pp.236-236
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• 2003

• Journal of the Korean Society of Radiology
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• v.7 no.5
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• pp.365-369
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• 2013

Intravenous injection is administered with radioactive medical isotopes to detect disease on Positron Emission Tomography (PET). In this case, typically, $^{18}FDG$ (Fluorodeoxyglucose) is used as a radioactive medicine. Cassette equipment is needed to synthesize deoxyglucose with $^{18}F$, produced by medical cyclotron. Production of radioactive medicine creates a lot of radiation, thus Hot Cell is used to shield a secondary radiation. We measured the radiation dosage flowing out of the hot cell during synthesis of $^{18}FDG$ or distribution. The purpose of this study is to provide the information of radiation dosage regarding the occupational exposure that unintentionally occurs during the synthesis of $^{18}FDG$. In conclusion, we confirmed the radiation dosage out of the hot cell during the $^{18}FDG$ synthesis. Especially, we observed that the radiation flowed out through the lead window, attached as a view port. Thus, it is considered that the improvement of a lead window is necessary in order to decrease the occupational exposure during the $^{18}FDG$ synthesis.

• Proceedings of the Korean Nuclear Society Conference
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• 2003.05a
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• pp.302-302
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• 2003

• Proceedings of the Korean Nuclear Society Conference
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• 2002.10a
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• pp.362.1-362
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• 2002

• Proceedings of the Korean Radioactive Waste Society Conference
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• 2012.10a
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• pp.159-160
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• 2012