• 제목/요약/키워드: Radiation level

검색결과 1,833건 처리시간 0.033초

Effects of Irradiation Temperature on the Sensory Quality Improvement of Gamma-irradiated Ganjang-gejang, Korean Traditional Marinated Raw Crab Portunus trituberculatus in Soybean Sauce

  • Park, Jae-Nam;Byun, Eui-Baek;Han, In-Jun;Song, Beom-Seok;Sohn, Hee-Sook;Park, Sang-Hyun;Byun, Eui-Hong;Yoon, Minchul;Sung, Nak-Yun
    • Fisheries and Aquatic Sciences
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    • 제18권2호
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    • pp.115-121
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    • 2015
  • This study was conducted to confirm quality properties of sterilized Ganjang-gejang (marinated crab Portunus trituberculatus) with Korean soy sauce using by gamma irradiation and to improve quality of sterilized Ganjang-gejang. The Ganjang-gejang was irradiated at dose of 3, 6, 9, 12, and 15 kGy by gamma irradiation and there was evaluated in microbiological, physicochemical, and sensory properties. Total aerobic bacteria and fungi contents of non-irradiated samples were about 6 and 4 log CFU/g level, respectively. Gamma-irradiated samples at above 9 kGy did not contain aerobic bacteria or fungi at detection limit less than 2 log CFU/g, but sensory scores were significantly decreased depending on the irradiation dose. To improve the sensory qualities of gamma-irradiated Ganjang-gejang, the temperature was adjusted during sample irradiation. When samples were irradiated under freezing temperatures, especially on dry ice, the TBARS and the deterioration of sensory qualities of Ganjan-Gejang were reduced. Different odor patterns were observed among samples, as observed using electronic nose analysis system. The results of this study indicated that treatment with irradiation under low temperatures may help to preparing high-quality Ganjang-gejang.

스키장의 자연방사선량 측정(경기도 지역을 중심으로) (Measurement of the Natural Radiation Dose in the Ski Field (Focusing on the Gyeonggi Province area))

  • 정홍문;정재은
    • 한국방사선학회논문지
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    • 제11권3호
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    • pp.117-122
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    • 2017
  • 레저생활의 급증으로 인하여 스키장 사용 인구가 급격히 증가하고 있다. 스키장은 직접적으로 자연광이나 우주선을 받을 확률이 높다. 왜냐하면 고도가 존재하는 산에 위치하기 때문이다. 일반적으로 고도가 높아질수록 자연방사선량이 증가한다는 사실은 널리 알려져 있다. 하지만 아직까지 스키장 고도에 관한 자연방사선량은 보고되지 않았다. 국내에는 다양한 스키장이 존재를 하지만 이번논문에서는 경기도 지역의 스키장4곳을 선정하여 고도에 따른 자연방사선량을 측정하였다. 결과적으로 스키장은 고도가 낮은 일반생활 지역에서보다는 방사선량보다 조금 많은 방사선량이 측정되었다. 우려할 수준은 아니지만 스키장 이용 시에는 반드시 스키 장비인 고글이나 다양한 스키 웨어(고글, 마스크, 헬멧)를 착용하여 자연방사선량을 보호한다면 환경방사선으로부터 안전하게 스키를 즐길 수 있을 것이다.

무인 원격 방사선 검출 모듈 개발 (Development of Unmanned Remote Radiation Detection Module)

  • 장보석
    • 한국방사선학회논문지
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    • 제15권6호
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    • pp.795-801
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    • 2021
  • 원전 해체 작업장의 요구에 따라 드론 기반 무인 원격 방사선 검출 모듈을 개발하였다. 사람이 접근해서 방사선을 측정할 수 없는 원자력 발전소 격납용기 내부 상공 및 외부로 누설되는 방사선 측정을 위한 목적으로 저준위에 민감한 GM-tube를 사용하여 제작하였다. 드론 기반 방사선 검출 모듈의 무게는 200g 미만으로 원자력 발전소 격납용기 내부의 상공과 외부 공중에서도 운용이 가능하다. 설계된 장비의 성능 확인을 위해 국제 기준 (IEC60864)을 참고하여 성능평가 실험을 시행하였다. 현장의 요구에 맞게 설계된 방사선 검출 모듈의 안정성은 측정 정확도를 평가하기 위한 변동률 실험에서 반복 측정에 의한 통계적 변동률은 ±4.6%. 선량률 의존성을 평가하기 위한 선형성 실험에서 정확도 ± 7.3%, 전체 선형도는 ± 3.5%이며 성능평가를 위한 국제기준을 만족하였다. 본 연구에서 개발한 무인 원격 방사선 검출 모듈은 원전 해체 작업장 맞춤형 장비로, 방사선 분진이 많은 현장에서 정확한 공간선량률의 측정과 방사선 작업장 안전관리에 도움을 줄 수 있을 것으로 확신한다.

LCD 제조공정의 이온화 장치에 대한 전리방사선 지역노출특성 분석 (Analysis of Local Exposure Levels of Radiation Emitted from Soft X-ray Ionizers in LCD Manufacturing Processes)

  • 김준범;정은교;정기효
    • 한국산업보건학회지
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    • 제31권4호
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    • pp.342-352
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    • 2021
  • Objectives: This study analyzed the local exposure levels of radiation emitted from the equipment with soft X-ray ionizers to investigate the radiation exposure levels in Liquid Crystal Display(LCD) manufacturing processes. Methods: This study measured the local radiation levels for the equipment installed in two LCD manufacturing companies. The equipment were installed at diverse processes and equipped with various number of ionizers. The local radiation levels were measured on the surface of the equipment by using direct reading equipment, and the measurements were converted into annual effective dose by considering the radiation exposure time of workers. Statistical analyses were performed to investigate the radiation exposure characteristics. Results: Annual effective doses for 97.6% of the equipment being measured were less than 1 mSv. However, the range of annual effective doses was 0.004 mSv ~ 2.167 mSv, which indicated a large variation among the equipment. Statistical analyses of the study found that this large variation was raised due to improper shielding of the equipment rather than process and/or equipment characteristics. To pinpoint the cause of this large variation in annual effective dose, this study improved the shielding of the equipment being radiated over 1 mSv and found that their average effective dose was reduced from 1.604 mSv to 0.126 mSv after shielding improvement. Conclusions: Relatively high exposure levels of radiation were observed in some equipment where their shielding were insufficiently thick and/or sealed. This finding implies that the shielding of the equipment is an important engineering countermeasure to control the radiation exposure levels in industries.

Assessment of Temporary Radioactivation for Tissue Expanders in Breast Radiation Therapy: Preliminary Study

  • Hwajung Lee;Do Hoon Oh;Lee Yoo;Minsoo Chun
    • Journal of Radiation Protection and Research
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    • 제48권2호
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    • pp.100-106
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    • 2023
  • Background: As breast tissue expanders consist of metallic materials in the needle guard and ferromagnetic injection port, irradiation can produce radioactivation. Materials and Methods: A CPX4 (Mentor Worldwide LLD) breast tissue expander was exposed using the Versa HD (Elekta) linear accelerator. Two photon energies of 6 and 10 MV-flattening filter free (FFF) beams with 5,000 monitor units (MU) were irradiated to identify the types of radiation. Furthermore, 300 MU with 10 MV-FFF beam was exposed to the CPX4 breast tissue expander by varying the machine dose rates (MDRs) 600, 1,200, and 2,200 MU/min. To assess the instantaneous dose rates (IDRs) solely from the CPX4, a tissue expander was placed outside the treatment room after beam irradiation, and a portable radioisotope identification device was used to identify the types of radiation and measure IDR. Results and Discussion: After 5,000 MU delivery to the CPX4 breast tissue expander, the energy spectrum whose peak energy of 511 keV was found with 10 MV-FFF, while there was no resultant one with 6 MV-FFF. The time of each measurement was 1 minute, and the mean IDRs from the 10 MV-FFF were 0.407, 0.231, and 0.180 μSv/hr for the three successive measurements. Following 10 MV-FFF beam irradiation with 300 MU indicated around the background level from the first measurement regardless of MDRs. Conclusion: As each institute room entry time protocol varies according to the working hours and occupational doses, we suggest an addition of 1 minute from the institutes' own room entry time protocol in patients with CPX4 tissue expander and the case of radiotherapy vaults equipped with a maximum energy of 10 MV photon beams.

Optimization of Yonsei Single-Photon Emission Computed Tomography (YSECT) Detector for Fast Inspection of Spent Nuclear Fuel in Water Storage

  • Hyung-Joo Choi;Hyojun Park;Bo-Wi Cheon;Kyunghoon Cho;Hakjae Lee;Yong Hyun Chung;Yeon Soo Yeom;Sei Hwan You;Hyun Joon Choi;Chul Hee Min
    • Journal of Radiation Protection and Research
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    • 제49권1호
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    • pp.29-39
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    • 2024
  • Background: The gamma emission tomography (GET) device has been reported a reliable technique to inspect partial defects within spent nuclear fuel (SNF) of pin-by-pin level. However, the existing GET devices have low accuracy owing to the high attenuation and scatter probability for SNF inspection condition. The purpose of this study is to design and optimize a Yonsei single-photon emission computed tomography version 2 (YSECT.v.2) for fast inspection of SNF in water storage by acquisition of high-quality tomographic images. Materials and Methods: Using Geant4 (Geant4 Collaboration) and DETECT-2000 (Glenn F. Knoll et al.) Monte Carlo simulation, the geometrical structure of the proposed device was determined and its performance was evaluated for the 137Cs source in water. In a Geant4-based assessment, proposed device was compared with the International Atomic Energy Agency (IAEA)-authenticated device for the quality of tomographic images obtained for 12 fuel sources in a 14 × 14 Westinghouse-type fuel assembly. Results and Discussion: According to the results, the length, slit width, and septal width of the collimator were determined to be 65, 2.1, and 1.5 mm, respectively, and the material and length of the trapezoidal-shaped scintillator were determined to be gadolinium aluminum gallium garnet and 45 mm, respectively. Based on the results of performance comparison between the YSECT.v.2 and IAEA's device, the proposed device showed 200 times higher performance in gamma-detection sensitivity and similar source discrimination probability. Conclusion: In this study, we optimally designed the GET device for improving the SNF inspection accuracy and evaluated its performance. Our results show that the YSECT.v.2 device could be employed for SNF inspection.

Implementation of Visible monkey into general-purpose Monte Carlo codes: MCNP, PHITS, and Geant4

  • Soo Min Lee;Chansoo Choi;Bangho Shin;Yumi Lee;Ji Won Choi;Bo-Wi Cheon;Chul Hee Min;Beom Sun Chung;Hyun Joon Choi ;Yeon Soo Yeom
    • Nuclear Engineering and Technology
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    • 제55권11호
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    • pp.4019-4025
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    • 2023
  • Recently, a new monkey computational phantom, called Visible Monkey, was developed for non-ionizing radiation studies in animal research. In this study, we extended its applications to ionizing radiation studies by implementing the voxel model of the Visible Monkey into three general-purpose Monte Carlo (MC) codes: MCNP6, PHITS, and Geant4. The implementation work for MCNP and PHITS was conducted using the LATTICE, UNIVERSE, and FILL cards. The G4VNestedParameterisation class was used for Geant4. Then, organ dose coefficients (DCs) for idealized photon beams in the antero-posterior direction were calculated using the three codes and compared, showing excellent agreement (differences <3%). Additionally, organ DCs in other directions (postero-anterior, left-lateral, and right-lateral) were calculated and compared with those of the newborn and 1-year-old reference phantoms. Significant differences were observed (e.g., the stomach DC of the monkey was 5-fold greater than that of the 1-year-old phantom at 0.03 MeV) while the differences tended to decrease with increasing energy (mostly <20% at 10 MeV). The results of this study allows conducting MC simulations using the Visible Monkey to estimate organ-level doses, which should be valuable to support/improve monkey experiments involving ionizing radiation exposures.

Measurement of Sonobuoy Transmitting Antenna System for Anti-Submarine Warfare

  • Min Kyeong-Sik
    • Journal of electromagnetic engineering and science
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    • 제5권2호
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    • pp.97-103
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    • 2005
  • This paper describes the measured results of sonobuoy transmitting antenna system for anti-submarine warfare (ASW). Since radiation pattern and power density depend on impedance matching between transmitting RF part and antenna with termination resistance, design of matching circuit is very important for sonobuoy system performance. Matching circuit is designed by Smith chart using control of L and C. In standing wave ratio(SWR) measurement using Network Analyzer, SWR of antenna with matching circuit observed 1.5 below at the assigned VHF band. It shows very excellent performance comparison with conversional product that is used for the same object. The measured vertical and horizontal radiation patterns are also shown the satisfaction of military specifications. A drop out of sonobuoy system on the sea is happened when angle of elevation direction is over 10 degrees, and it is conformed that it takes less than I second return to original signal level. The required electric power density is $83\;mW/m^2$ in the military specification, and measured electric power density is observed over average $110\;mW/m^2$ at all frequency bands.

EVALUATION OF THE UNCERTAINTIES IN THE MODELING AND SOURCE DISTRIBUTION FOR PRESSURE VESSEL NEUTRON FLUENCE CALCULATIONS

  • Kim, Yong-Il;Hwang, Hae-Ryong
    • Journal of Radiation Protection and Research
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    • 제26권3호
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    • pp.237-241
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    • 2001
  • The uncertainties associated with fluence calculation at the pressure vessel have been evaluated for the Korean Next Generation Reactor, APR1400. To obtain uncertainties, sensitivity analyses were performed for each of the parameters important to calculated fast neutron fluence. Among the important parameters to the overall uncertainties, reactor modeling and core neutron source were examined. Mechanical tolerances, composition and density variations in the reactor materials as well as application of $r-{\theta}$ geometry in rectilinear region contribute to uncertainty in the reactor modeling. Depletion and buildup of fissile nuclides, instrument error related to core power level, uncertainty of fuel pin burnup, and variation of long-term axial peaking factors are main contributors to the core neutron source uncertainty. The sensitivity analyses have shown that the uncertainty in the fluence calculation at the reactor pressure vessel is +12%.

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수질 영향평가 신뢰수준 향상을 위한 낙동강 유역 미관측 지점에서의 일사량 추정: 수정형 Angstrom모형과 투과율모형의 비교 (Estimation of Daily Solar Radiation at the Missing Point for Water Quality Impact Assessment in Nakdong River Watershed: Comparison of Modified Angstrom Model and Transmittance interpolation Model)

  • 이길하
    • 환경영향평가
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    • 제21권1호
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    • pp.219-227
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    • 2012
  • Daily solar radiation is essential for water resources planning and environmental impact assessment. However, radiation data is not commonly available in Korea other than in big cities, and there has been no direct measurement for rural areas where water resources planning and environmental impact assessment is usually most needed. In general, missing radiation data is estimated from nearby regional stations within a certain distance, and this study compared two dominant methods (modified Angstrom equation and transmittance interpolation method) at six stations in Nakdong River watershed area. Two methods shows a similar level of accuracy but the transmittance interpolation method is likely to be superior in that there is no need for any measurement element since the modified Angstrom equation require the sunshine hour measurement. This study will contribute to improve water resource and water quality management in Nakdong River watershed.