• Proceedings of the Korean Society of Medical Physics Conference
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• 2004.11a
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• pp.33-35
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• 2004

방사선치료를 위한 고에너지 광자선의 품질관리를 위해 사용하는 TLD의 광자선 선질에 대한 에너지 의존도를 몬테카를로 모사법을 사용하여 평가하였다. IAEA 선량보증사업에 이용되는 LiF TLD 및 홀더를 EGS4기반의 사용자 코드인 DOSIMETER 와 MCNP4C 몬테카를로 코드를 사용하여 기하학구조를 구성하고, Co, 4, 6,10 밑 15 MV 광자선을 시뮬레이션하였다. DOSIMETER계산 결과를 통해 TLD의 에너지 보정인자가 실험 데이터와 일치함을 확인할 수 있었으며, 이와 별도로 캡슐에 의한 교란량도 무시할 수 없음을 발견하였다.

• Proceedings of the Korean Nuclear Society Conference
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• 1997.10a
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• pp.197-202
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• 1997

ORIGEN2코드의 검증계산을 통해 PWR 사용 후 핵연료 조성핵종의 핵종량에 대한 핵임계측면에서 보수성을 가지는 안전인자를 산출하였고, MCNP코드의 검증계산으로 95/95 신뢰구간에서의 계산오차를 구하였다. 이를 바탕으로 직경이 1.2567cm이고 길이가 380.5cm인 196 개 금속봉을 장전한 캐니스터 ( 금속저장체 )가 x-y 방향으로 무한히 배열된 경우에 대해 캐니스터의 두께, 간격 및 외부의 공기중 수분농도에 따른 핵임계 안전해석을 수행하였다. 그 결과, 캐니스터의 두께가 7mm일 때 공기중 수분농도가 0.30 g/㎤이고 캐니스터간의 간격이 6.0cm인 경우의 최종핵 임계도값은 0.94130로서 최대허용핵임계값 (0.942)보다 적은 값을 보였다.

• Proceedings of the Korean Nuclear Society Conference
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• 2004.10a
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• pp.71-72
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• 2004

• Proceedings of the Korean Radioactive Waste Society Conference
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• 2012.05a
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• pp.379-380
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• 2012

• Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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• v.13 no.1
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• pp.55-61
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• 2015

When a radiation detector is applied to the measurement of the radioactivity of high-level of radioactive materials or the rapid response to the nuclear accident, several collimators with the different inner radii should be prepared according to the level of dose rate. This makes the in-situ measurement impractical, because of the heavy weight of the collimator. In this study, an IRIS collimator was developed so as to have a function of controlling the inner radius, with the same method used in optical camera, to vary the attenuation ratio of radiation. The shutter was made to have the double tungsten layers with different phase angles to prevent the radiation from penetrating owing to the mechanical tolerance. The performance evaluation through the MCNP code was conducted by calculating the attenuation ratio according to the inner radius of the collimator. The attenuation ratio was marked on the outer scale ring of the collimator. It is expected that when a radiation detector with the IRIS collimator is used for the in-situ measurement, it can change the attenuation ratio of the incident photon to the detector without replacing the collimator.

• Nuclear Engineering and Technology
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• v.21 no.2
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• pp.63-72
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• 1989

An analysis for the gamma radiation fields in the research reactor MAPLE-X10 facility has been peformed under the assumption of partial loss of reactor and service pool water to assess the safety from the view point of design. Four photon source terms considered in the analysis were calculated using the ORIGEN-S code. Gamma dose rate calculations over the reactor and service pools during the water-loss accident conditions were performed using QAD-CG code. MCNP code (Monte Carlo Neuron and Photon Transport code), also, was used to assess the scattered radiation fields away from the pools, which is appropriate for calculating the scattered photon dose rates outside of the solid angle subtended by the source and pool walls.

• Korean Journal of Environmental Biology
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• v.24 no.4
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• pp.387-391
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• 2006

Computational and experimental dosimetry of Henschke applicator with respect to high dose rate brachytherapy using the MIRD phantom and a remote control afterloader were performed. A comparison of computational dosimetry was made between the simulated Monte Carlo dosimetry and GAMMADOT brachytherapy Planning system's dosimetry. Dose measurements was performed using ion chamber in a water phantom. Dose rates are calculated using Monte Carlo code MCNP4B and the GAMMADOT. Thecomputational models include the detailed geometry of Ir-192 source, tandem tube, and shielded ovoids for accurate estimation. And transit dose delivered during source extension to and retraction from a given dwell position was estimated by Monte Carlo simulations. Point doses at ICRU bladder/rectal pointswhich have been recommened by ICRU 38 was assessed. Calculated and measured dose distribution data agreed within 4% each other. The shielding effect of ovoids leads to 19% and 20% dose reduction at bladder surface and rectal points.

• Proceedings of the Korean Institute of Information and Commucation Sciences Conference
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• 2013.05a
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• pp.1017-1019
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• 2013

The radiation sources leaked from large-scale radiation leak accident like the Hukushima nuclear power plant accident or nuclear explosions can cause to the very large damage for us. So that the damage can be minimized, we have being developed a detector that can providing information about the location of the source to remove dangerous substances quickly than the conventional single detector. In this paper, we designed the shielding and collimator for the development of the Stereo Radiation detector in order to detect contaminants using MCNP Code. And we analyzed the results that is detected from the discretionary position of the radiation source. The results of this paper will be used as the basis for designing efficient structure for the radiation detectors.

• Proceedings of the Korean Institute of Information and Commucation Sciences Conference
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• 2013.05a
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• pp.1031-1033
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• 2013

Radiation protection, as well as finding the location of the radiation source, such as the Fukushima radiation leak accident, it is important for the early and safe disposal of nuclear accident. The three-dimensional position of the radiation source detection distance of the radiation source can provide additional information to the existing radiation detectors radiation of a two-dimensional position detection function and then it can play a decisive role in the radiation contaminant removal and decontamination work. In this research, three-dimensional semiconductor sensor based on dual radiation detectors radiation source device visible part of the research and development of efficient radiation sensor unit on the design of the shielding structure.The lightweight, high-efficiency radiation source locator implementation was attempted for the structure and thickness of the shielding and collimator to perform the simulation of the radiation shielding for the various parameters of the shape model through design the optimal structure of the MCNP-based heavy-duty tungsten shielding, lead shielding The results of this study, is a compact, lightweight three-dimensional radiation source detection and future of silicon - based sensors will be used in the study.

• Proceedings of the Korean Nuclear Society Conference
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• 1995.10a
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• pp.73-78
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• 1995

이중 또는 삼중으로 탄소 피막된 핵연료 입자를 Graphite 소결체에 채워넣은 핵연료를 설계하고, 이에 대한 핵적 타당성을 검토하고자 하였다. 핵계산 체계로서 CASMO-3가 갖는 Spatial Self-shielding 효과의 문제, 코드의 계산 방식 문제, 핵자료 결손 문제를 검토한 후 보정 계수를 산출하려 하였다. CASMO-3의 정확도는 MCNP-4A를 통해 검증하였는데, 비균질한 소결체 내부를 균질화 함으로서 야기되는 Spatial Self-Shielding 효과는 임계도의 차이가 거의 없는 것으로 확인되어졌고, 계산 코드의 차이로 인한 효과 또한 무시할 수 있었다. 그러나 CASMO-3의 핵자료에서 탄소와 실리콘의 자료 부족은 임계도 차이가 0.06184정도로 다소 차이가 나기 때문에 보정이 필요함을 확인하였으나 CASMO-3 자체의 유용성에는 문제가 없었다.