• 제목/요약/키워드: Radiation transport

검색결과 401건 처리시간 0.022초

노외 감시자를 이용한 압력용기 중성자 조사량 결정 (Fast Neutron Flux Determination by Using Ex-vessel Dosimetry)

  • 유춘성;박종호
    • Journal of Radiation Protection and Research
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    • 제32권4호
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    • pp.158-167
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    • 2007
  • 본 논문의 목적은 노외 중성자 선량 감시자를 이용하여 원자로 압력용기 중성자 조사취화의 핵심 요인이 되는 고속중성자 ($1{\ge}MeV$) 조사량 평가 방법을 제시하고 적용성을 검증하는 것이다. 다양한 중성자 반응에너지를 갖는 다수의 선량감시자를 원자로 외벽 보온 단열재와 1차 생물학적 차폐체 사이의 공간에 설치하고 한 주기 동안 조사시킨 후 인출하여 생성핵종에 대한 방사선을 측정하여 반응률을 도출하였다. 또한 상업용 코드를 이용한 중성자 수송계산을 통해 감시자 위치에서의 중성자 스펙트럼을 계산하였다. 두 결과로부터 감시자에 대한 반응률을 직접 비교할 수 있었으며 또한 최소자승 조정 절차를 통해 최적의 중성자 스펙트럼도 도출할 수 있었다. 감시자 측정 결과와 해석적으로 계산한 중성자 조사량 사이에는 관련 규정에서 제시한 ${\pm}30%$ 이내의 오차를 보였다.

The Detection of Yellow Sand Using MTSAT-1R Infrared bands

  • Ha, Jong-Sung;Kim, Jae-Hwan;Lee, Hyun-Jin
    • 대한원격탐사학회:학술대회논문집
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    • 대한원격탐사학회 2006년도 Proceedings of ISRS 2006 PORSEC Volume I
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    • pp.236-238
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    • 2006
  • An algorithm for detection of yellow sand aerosols has been developed with infrared bands from Moderate Resolution Imaging Spectroradiometer (MODIS) and Multi-functional Transport Satellite-1 Replacement (MTSAT-1R) data. The algorithm is the hybrid algorithm that has used two methods combined together. The first method used the differential absorption in brightness temperature difference between $11{\mu}m$ and $12{\mu}m$ (BTD1). The radiation at 11 ${\mu}m$ is absorbed more than at 12 ${\mu}m$ when yellow sand is loaded in the atmosphere, whereas it will be the other way around when cloud is present. The second method uses the brightness temperature difference between $3.7{\mu}m$ and $11{\mu}m$ (BTD2). The technique would be most sensitive to dust loading during the day when the BTD2 is enhanced by reflection of $3.7{\mu}m$ solar radiation. We have applied the three methods to MTSAT-1R for derivation of the yellow sand dust and in conjunction with the Principle Component Analysis (PCA), a form of eigenvector statistical analysis. As produced Principle Component Image (PCI) through the PCA is the correlation between BTD1 and BTD2, errors of about 10% that have a low correlation are eliminated for aerosol detection. For the region of aerosol detection, aerosol index (AI) is produced to the scale of BTD1 and BTD2 values over land and ocean respectively. AI shows better results for yellow sand detection in comparison with the results from individual method. The comparison between AI and OMI aerosol index (AI) shows remarkable good correlations during daytime and relatively good correlations over the land.

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Dose coefficients of mesh-type ICRP reference computational phantoms for external exposures of neutrons, protons, and helium ions

  • Yeom, Yeon Soo;Choi, Chansoo;Han, Haegin;Shin, Bangho;Nguyen, Thang Tat;Han, Min Cheol;Kim, Chan Hyeong;Lee, Choonsik
    • Nuclear Engineering and Technology
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    • 제52권7호
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    • pp.1545-1556
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    • 2020
  • Recently, the International Commission on Radiological Protection (ICRP) has developed the Mesh-type Reference Computational Phantoms (MRCPs) for adult male and female to overcome the limitations of the current Voxel-type Reference Computational Phantoms (VRCPs) described in ICRP Publication 110 due to the limited voxel resolutions and the nature of voxel geometry. In our previous study, the MRCPs were used to calculate the dose coefficients (DCs) for idealized external exposures of photons and electrons. The present study is an extension of the previous study to include three additional particles (i.e., neutrons, protons, and helium ions) into the DC library by conducting Monte Carlo radiation transport simulations with the Geant4 code. The calculated MRCP DCs were compared with the reference DCs of ICRP Publication 116 which are based on the VRCPs, to appreciate the impact of the new reference phantoms on the DC values. We found that the MRCP DCs of organ/tissue doses and effective doses were generally similar to the ICRP-116 DCs for neutrons, whereas there were significant DC differences up to several orders of magnitude for protons and helium ions due mainly to the improved representation of the detailed anatomical structures in the MRCPs over the VRCPs.

5 L급 액체수소 저장용기의 성능특성 연구 (Performance of a 5 L Liquid Hydrogen Storage Vessel)

  • 강상우;나다니엘 가르소;임창무;백종훈;김서영;오인환
    • 한국수소및신에너지학회논문집
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    • 제26권3호
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    • pp.234-240
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    • 2015
  • In the face of the world's growing energy storage needs, liquid hydrogen offers a high energy density solution for the storage and transport of energy throughout society. A 5 L liquid hydrogen storage tank has been designed, fabricated and tested to investigate boil-off rate of liquid hydrogen. As the insulation plays a key role on the cryogenic vessels, various insulation methods have been employed. To reduce heat conduction loss, the epoxy resin-based insulation supports G-10 were used. To minimize radiation heat loss, vapor cooled radiation shield, multi-layer insulation, and high vacuum were adopted. Mass flow meter was used to measure boil-off rate of the 5 L cryogenic vessel. A series of performance tests were done for liquid nitrogen and liquid hydrogen to compare with design parameters, resulting in the boil-off rate of 1.7%/day for liquid nitrogen and 16.8%/day for liquid hydrogen at maximum.

300 keV 중성자(中性子)에 대한 방사선량(放射線量) 관계량(關係量)의 산정(算定) (Dosimetric Quantities for 300 keV Neutrons)

  • 이수용
    • Journal of Radiation Protection and Research
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    • 제11권1호
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    • pp.37-43
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    • 1986
  • ICRU 구(球)를 피사체(被射體)로 하여 300 keV 중성자(中性子)의 방사선량(放射線量) 관계량(關係量)을 평가(評價)하였다. 피사체내(被射體內)의 선량당량(線量當量) 분포(分布)를 직접(直接) 산정(算定)하기 위해 중성자(中性子)-광자(光子)-하전입자(荷電粒子) 결합수송(結合輸送)을 다룰 수 있는 몬테칼로 코드 NEDEP을 사용하였다. 계산결과(計算結果) 얻은 방사선량(放射線量) 관계량(關係量)은 다음과 같다. 심부선량당량지수(深部線量當量指數) $H_{I,d}:1.78{\times}10^{11}\;Sv-cm^2$ 표층선량당량지수(表層線量當量指數) $H_{I,s}:2.08{\times}10^{-1}\;Sv-cm^2$ 주위선량당량(周圍線量當量) $H^*(0.07):1.70{\times}10^{-11}\;Sv-cm^2$ 주위선량당량(周圍線量當量) $H^*(10):1.78{\times}10^{-11}\;Sv-cm^2$ 실효선질계수(實效線質係數) $\bar{Q}^*(10):12.4$

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Feasibility of Intra-Operative BNCT Using Accelerator-Based Near-Threshold $^7Li(p,n)^7$Be Direct Neutrons

  • Tanaka, Kenichi;Kobayashi, Tooru;Nakagawa, Yoshinobu;Sakurai, Yoshinori;Ishikawa, Masayori;Hoshi, Masaharu
    • 한국의학물리학회:학술대회논문집
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    • 한국의학물리학회 2002년도 Proceedings
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    • pp.157-160
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    • 2002
  • The dosage of intra-operative BNCT using near-threshold $^{7}$ Li(p,n)$^{7}$ Be direct neutrons was evaluated with the calculation method validated with the phantom experiment. The production of both neutrons by near-threshold $^{7}$ Li(p,n)$^{7}$ Be and gamma rays by $^{7}$ Li(p,p'gamma)$^{7}$ Li in a Li target was calculated using Lee's method and their transport in the phantom was calculated with MCNP-4B. As a result, the region satisfying the requirements of the protocol in intra-operative BNCT for brain tumors in Japan was acknowledged to be comparable to present BNCT, for the proton energy of 1.900 MeV for example. A boron-dose enhancer (BDE) introduced in this study to increase $^{10}$ (n,$\alpha$)$^{7}$ Li dose in a living body was effective. The void used to increase doses in deep regions was also valid with the BDE. It was found that intra-operative BNCT using near-threshold $^{7}$ Li(p,n)$^{7}$ Be direct neutrons is feasible.

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핵연료(核燃料) 수송용기(輸送容器)에 대(對)한 핵림계분석(核臨界分析) (Criticality Analyses of Spent Fuel Shipping Cask)

  • 민덕기;노성기;곽은호
    • Journal of Radiation Protection and Research
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    • 제9권2호
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    • pp.97-102
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    • 1984
  • KSC-1 핵연료(核燃料) 수송용기(輸送容器)에 대(對)한 핵림계분석(核臨界分析)을 KENO-IV 몬테칼로 전산(電算)코드와 AMPX 전산(電算)코드계(系)로 부터 생산(生産)한 CSLIB 19 19-에너지군(群) 단면적(斷面積) 자료(資料)를 써서 수행(修行)하였다. 이때 미국(美國) B&W 사(社) CX-10 핵림계장치(核臨界裝置)를 대상으로 하여 KENO-IN 및 CSLIB 19단면적(斷面積) 시스템에 대한 검증계산(檢證計算)을 수행(遂行)한 후(後), 이 시스템의 타당성을 먼저 확인(確認)하였다. 핵림계분석(核臨界分析) 결과(結果), 1개(個)의 가압경수로(加壓輕水爐) 사용후(使用後) 핵연료집합체(核燃料集合體)를 운반할 수 있는 핵연료수송용기(核燃料輸送容器)는 정상적(正常的)인 수송조건(輸送條件)뿐만 아니라 가상적(假想的)인 수송사고조건하(輸送事故條件河)에서도 핵림계(核臨界)에 관(關)한 한(限) 안전(安全)한 것 같았다.

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Monte Carlo Simulation of Phytosanitary Irradiation Treatment for Mangosteen Using MRI-based Geometry

  • Oh, Se-Yeol;Kim, Jongsoon;Kwon, Soon-Hong;Chung, Sung-Won;Kwon, Soon-Goo;Park, Jong-Min;Choi, Won-Sik
    • Journal of Biosystems Engineering
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    • 제39권3호
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    • pp.205-214
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    • 2014
  • Purpose: Phytosanitary irradiation treatment can effectively control regulated pests while maintaining produce quality. The objective of this study was to establish the best irradiation treatment for mangosteen, a popular tropical fruit, using a Monte Carlo simulation. Methods: Magnetic resonance image (MRI) data were used to generate a 3-D geometry to simulate dose distributions in a mangosteen using a radiation transport code (MCNP5). Microsoft Excel with visual basic application (VBA) was used to divide the image data into seed, flesh, and rind. Radiation energies used for the simulation were 10 MeV (high-energy) and 1.35 MeV (low-energy) for the electron beam, 5 MeV for X-rays, and 1.25 MeV for gamma rays from Co-60. Results: At 5 MeV X-rays and 1.25 MeV gamma rays, all areas (seeds, flesh, and rind) were irradiated ranging from 0.3 ~ 0.7 kGy. The average doses decreased as the number of fruit increased. For a 10 MeV electron beam, the dose distribution was biased: the dose for the rind where the electrons entered was $0.45{\pm}0.03$ kGy and the other side was $0.24 {\pm}0.10$ kGy. Use of an electron kinetic energy absorber improved the dose distribution in mangosteens. For the 1.35 MeV electron beam, the dose was shown only in the rind on the irradiated side; no significant dose was found in the flesh or seeds. One rotation of the fruit while in front of the beam improved the dose distribution around the entire rind. Conclusion: These results are invaluable for determining the ideal irradiation conditions for phytosanitary irradiation treatment of tropical fruit.

미생물의 세포생리에 미치는 전이방사선의 영향에 관한 연구 (제 4 ) -효모균의 수화물대 에 대한 $\gamma$-의 영향에 대하여- (Studies on the cellular metabolism in microorganisms as influenced by gamma-irradiation.(IV) "on the carbohydrate metabolism of yeast irradiated by $\gamma$-ray.")

  • 김종협
    • 미생물학회지
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    • 제6권2호
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    • pp.41-53
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    • 1968
  • Studies on the carbohydrate metabolism of yeast as influenced by gamma-irradiation from cobalt-60 have been carried, then the mechanisms of radiation effect on respiration and fermentation were discussed under considerations of permeable changes of irradiated cell membrane. The cells of baker's yeast (Saccharomyces cerevisiae) which had been gamma-irradiated of 240 k.r. doses for an hour, then were put into aerobic oxidation and anaerobic fermentation without substrate. Total and fractionated carbohydrates of irradiated yeast cells were determined by calorimetric method with anthrone and orcinol reagents, the amounts of total carbohydrate, trehalose, RNA-ribose, PCA-soluble glycogen, alkali-soluble glycogen, acetic acid-soluble glycogen, mannan and glucan were determined according to the course of aerobic oxidation and anaerobic fermentation. It is found that the carbohydrates of irradiated cells leak out and amount of the losses teaches eleven times more than that of control, the volume of losses are seems to be replaced by water, it can be suggested the damage of gamma-irradiation occurs in the site of passive transport of cell membrane. The endogeneous aerobic respiration of irradiated cells are increased much more than control, the synthesis of reserve glycogen, glucan and RNA-ribose promoted much more than control. The anaerobic fermentation of irradiated cells are also increased than that of control, but the breakdown of carbohydrate is less than endogeneous respiration of irradiated cells. The synthetic rate is also less than that of aerobic oxidation. In irradiated yeast cells, trehalose is revealed to be primary substrate for endogeneous carbohydrate metabolism, so it is proved that the enzymic patterns are not changed but the activities of enzymes relating endogeneous respiration and autofermentation is activated. It is to be considerable to distiguish endogeneous respiration and autofermentation from exogeneous respiration and fermentation on irradiation, for membrane permeability changes and loses out carbohydrate by ionizing radiation.

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특수형 방사성 동위원소 운반캡슐의 안전성 평가 (Safety Evaluation of a Shipping Capsule for Special Form Radioisotope)

  • 이주찬;서기석;구정회;방경식;한현수;박성원
    • Journal of Radiation Protection and Research
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    • 제26권1호
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    • pp.35-43
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    • 2001
  • 특수형 방사성물질 운반캡슐은 국내외의 수송관련 법규에 규정된 기술기준을 만족하도록 설계, 제작되어야 한다. 본 연구의 목적은 하나로에서 생산된 $^{192}Ir$ 특수형 등위원소 운반캡슐의 건전성을 평가하는데 있다. 법규에서 규정된 낙하시험, 타격시험, 굽힘시험 및 가열시험조건에 대한 안전성 시험을 수행하였으며, 각각의 시험 전후에 누설시험을 수행하였다. 또한, 안전성시험과 더불어 컴퓨터코드를 이용한 전산해석을 수행하여 안전성시험 전에 시험결과에 대한 예측자료로 활용되었다. 낙하시험 및 가열시험 결과 캡슐 표면에서 약간의 흠집과 변형이 발생하였으나, 각각의 시험에서 평가기준이 되는 캡슐의 손상이나 용융 등은 발생하지 않았다. 또한 각 시험 후 수행한 누설시험 결과 누설이 발생하지 않았다. 따라서 특수형 방사성물질 운반캡슐은 법규에서 규정하는 기술기준을 만족하도록 설계, 제작되었음이 입증되었다.

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