• Nuclear Engineering and Technology
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• 제53권5호
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• pp.1519-1523
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• 2021

Radioactive iodine (¹³¹I) released from nuclear power plants has been a critical environmental concern for workers. The effective trapping of radioactive iodine isotopes from the off-gas stream generated from nuclear facilities is an important issue in radioactive waste treatment systems evaluation. Numerous studies on retaining methyl iodide (CH₃I¹³¹) by impregnated activated carbons under the high content of moisture have been extensively studied so far. But there have been no good results on how to remove methyl iodide at high humid conditions up to now. A new challenge is to introduce other promising impregnating chemical agents that are able to uptake enough radioactive methyl iodide under high humid conditions. In order to develop a good removal efficiency to control radioiodine gas generated from a high humid process, activated carbons (ACs) impregnated with triethylene diamine (TEDA) and qinuclidine (QUID) were prepared. In addition, the removal efficiencies of the activated carbons (ACs) under humid conditions up to 95% RH were evaluated by applying the standard method specified in ASTM-D3808. Quinuclidine impregnated activated carbon showed a much higher decontamination factor above 1,000, which is enough to meet the regulation index for the iodine filters in nuclear power plants (NPPs).

• 한국방사성폐기물학회:학술대회논문집
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• 한국방사성폐기물학회 2004년도 Proceedings of the 4th Korea-China Joint Workshop on Nuclear Waste Management
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• pp.51-59
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• 2004

The geological research as a part of HLW disposal program in Korea is carried out to provide necessary data for the establishment of the reference repository system in term of design and safety assessment in the crystalline rock terrains. Six deep boreholes were drilled to obtain hydrogeological and hydrochemical data from Jurassic granites in the Yuseong area, Korea. The core observation, televiewer logging and hydraulic testing were carried out during and after drilling and multi-packer system were installed in the boreholes of 500m depth for hydraulic and hydrochemical monitoring including environmental isotopes. The integration of hydrogeochemical and hydrodynamic data would be built greater confidence for the understanding of groundwater system in fractured rock mass. This geoscientific program could be possible to suggest a general guideline to develop the reference disposal concept of high-level radioactive waste in Korea.

• Nuclear Engineering and Technology
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• 제54권7호
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• pp.2690-2701
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• 2022

In this paper, we select important fission products for the estimation of the source term during a severe accident of a PWR. The selection is based on the numerical results obtained from depletion calculations for the typical PWR fuel via the in-house code named DEGETION (Depletion, Generation, and Transmutation of Isotopes on Nuclear Application), release fractions of the fission products derived from NUREG-1465, and effective dose conversion coefficients from ICRP 119. Then, for the selected fission products, we obtain the adjoint solutions of the Bateman equations for radioactive decay in order to determine the importance of precursors producing the aforementioned fission products via radioactive decay, which would provide insights into the assumption used in MACCS 2 for a level 3 PSA analysis in which up to six precursors are considered in the calculations of radioactive decays for the fission product after release from the reactor.

• The Korean Journal of Ceramics
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• 제4권2호
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• pp.90-94
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• 1998

Self diffusion coefficients of $^{67}$Co and impurity diffusion coefficients of $^{51}$Mn and $^{65}$Zn in single crystalline CoO have been measured by applying different radioactive isotopes simultaneously. To compare the residual activity method and the tracer sectioning method we analyzed our tracer diffusion experiments by using both methods simultaneously. According to our experimental results, the diffusion coefficients obtained from both methods are identical within experimental error, demonstrating the relibility of our experimental procedures. The diffusion coefficients of all the isotopes obtained during these test experiments for the methodology are similar in magnitude and show similar dependences on oxygen partial pressure. These first observations indicate that impurity diffusion of Mn and Zn occur via a vacancy mechanism as known for self diffusion of cobalt.

• 지구물리와물리탐사
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• 제24권1호
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• pp.20-27
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• 2021

암석의 열생산율은 구성 광물 내 방사성 동위원소의 방사성 붕괴와 감마선 방출에 의한 열에너지에 기인하며, 그 크기는 주요 방사성 동위원소인 U, Th, K의 함량에 지배적이다. 그러므로 암반의 열생산율은 암석의 밀도와 주요 동위원소의 함량에 기반해 평가할 수 있다. 심부 암반의 열생산율 평가에 필요한 방사성 동위원소의 농도는 시추공에서 회수된 암추 또는 암편에 대한 질량분석을 통해 파악할 수 있는데, 대심도 시추공의 경우 요구되는 분석량과 그에 따른 시간 및 비용의 문제로 적용이 제한적일 수 밖에 없다. 시추공을 대상으로 하는 물리검층 중 암반의 감마선 스펙트럼으로부터 U, Th, K의 함량을 유추할 수 있는 기술이 있지만, 열생산율 평가를 위해 별개의 밀도검층 자료를 필요로 하며, 상용화된 장비의 적용 심도 또한 아직은 제한적이다. 이에 대한 대안으로 시추공 암반이 방출하는 감마선의 강도를 측정하는 자연 감마선 검층 결과로부터 열생산율을 유추하는 방법이 제안된 바 있으며, 국내외에서 비교적 쉽게 암반의 열생산율을 평가할 수 있는 방법으로 사용되고 있다. 본 기술보고에서는 국내 상용화된 대심도 시추공 물리검층 장비 및 기술을 활용해 감마선 검층 기반의 열생산율 평가 기법을 개발하고, 국내 약 2 km 깊이의 대심도 시추공에 대한 적용 및 검증 사례를 소개하고자 한다.

• 대한방사선기술학회지:방사선기술과학
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• 제18권1호
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• pp.81-90
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• 1995

This study was conducted to find out the management status of radioisotopes and radioactive waste products in Korean medical institutions during the period of three years from 1991 to 1993. The results are summarized as follows : 1. The rate of medical institution to the institutions making use of radioisotopes was decreased every year, for example, 18.11 % in the year 1991, 17.86 % in the year 1992 and 15.87 % in the year 1993. 2. The use of domestic made radioisotopes in the medical institution was increased every year, for instance, 89.68 % in the year 1991, 94.21 % in the year 1992 and 99.79 % in the year 1993. 3. 91.01 % of the half life of isotopes used in the medical Institution were two month below. 4. The rate of radioactive waste products in the medical institution to all radioactive waste products was increased every year, for example, 54.44 % in the year 1991, 75.36 % in 1992 and 78.49 % in the year 1993. 5. The rate of inflammable waste products from medical institution was 76.47 % of all inflammable waste products, and 73.99 % of whole waste products was from the medical Institution.

• Journal of Radiation Protection and Research
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• 제41권4호
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• pp.350-353
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• 2016

Background: Various characteristics such as size distribution, chemical component and radio-activity have been analyzed for radioactive aerosols released from Fukushima Daiichi Nuclear Power Plant. Measured results for radioactive aerosols suggest that the potential transport medium for radioactive cesium was non-sea-salt sulfate. This result indicates that cesium isotopes would preferentially attach with sulfate compounds. In the present work the attachment behavior of fission products to aqueous solution aerosols of sodium salts has been studied using a generation system of solution aerosols and spontaneous fission source of $^{248}Cm$. Materials and Methods: Attachment ratios of fission products to the solution aerosols were compared among the aerosols generated by different solutions of sodium salt. Results and Discussion: A significant difference according as a solute of solution aerosols was found in the attachment behavior. Conclusion: The present results suggest the existence of chemical effects in the attachment behavior of fission products to solution aerosols.

• Journal of Radiation Protection and Research
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• 제5권1호
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• pp.11-25
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• 1980

The increasing utilization of radioactive isotopes in industry, medicine and research has raised the question, 'How should hospitals deal with radiation injuries when they occur?' A system for initial management of radiation injuries has been developed by Radiation Management Corporation. Radiation injuries are classified and a treatment plan outlined for each at the emergency and short term medical care phase. This system includes clinical prognosis as well as a detailed plan for quick set up or a Radiation Emergency Area in any hospital. Procedures for patient admission, preparation of the facility, general decontamination, sample taking, and wound decontamination are included.

• 한국원자력학회:학술대회논문집
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• 한국원자력학회 2005년도 춘계학술발표회
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• pp.271-272
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• 2005

• Journal of Radiation Protection and Research
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• 제19권3호
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• pp.209-221
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• 1994

원자력발전소의 중대 사고시 대기로 방출된 방사성물질에 의해 피폭자가 사고후 일생동안 받게 될 전신 피폭선량과 핵종의 상대적 중요도를 방출점으로부터 거리에 따라 각 피폭경로에 대해 평가하였다. 방사능운과 지표에 침적된 방사성물질에 의한 외부피폭, 호흡과 오염된 음식물섭취에 의한 내부피폭이 피폭경로로 고려되었다. 오염된 음식물섭취에 의한 영향은 우리나라 환경을 고려하여 개발된 동적 삽식경로모델 KORFOOD을 사용하여 침적시점과 침적후 시간에 따른 음식물내 방사성물질의 농도 변화를 고려하였다. 방출점으로부터 80km까지 피폭선량을 평가한 결과, 오염된 음식물섭취에 의한 영향이 가장 높았다. 핵종별 기여도는 방사능운에 의한 외부피폭과 호흡에 의한 내부피폭의 경우 I, 침적된 방사성물질에 의한 외부피폭의 경우 Cs에 의한 영향이 가장 높았다. 오염된 음식물섭취에 의한 내부피폭의 경우 Cs은 여름철 침적, Sr은 겨울철 침적에 보다 중요한 영향을 미쳤다.