• 대한안전경영과학회:학술대회논문집
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• 대한안전경영과학회 2011년도 추계학술대회
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• pp.85-91
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• 2011

Safety in the nuclear facility has been a growing interest due to recent recurrences of the fatal accidents such as Fukushima accident and Chernobyl accident. It is not easy to determine the extent to what technical requirements of nuclear facility such as nuclear power plant are be likely applicable to the laboratory for use of nuclear material. All of workers in nuclear shall be recognized for the generic features of safety according to the related laws. This study surveys a status of safety control laws to enhance safety in laboratory for use of nuclear material.

• Nuclear Engineering and Technology
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• 제49권5호
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• pp.1010-1018
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• 2017

The European Treatment and Disposal of Irradiated Graphite and other Carbonaceous Waste project sought to develop best practices in the retrieval, treatment, and disposal of irradiated graphite including other irradiated carbonaceous waste such as structural material made of graphite, nongraphitized carbon bricks, and fuel coatings. Emphasis was given on legacy irradiated graphite, as this represents a significant inventory in respective national waste management programs. This paper provides an overview of the characteristics of graphite irradiated during its use, primarily as a moderator material, within nuclear reactors. It describes the potential techniques applicable to the retrieval, treatment, recycling/reuse, and disposal of these graphite wastes. Considering the lifecycle of nuclear graphite, from manufacture to final disposal, a number of waste management options have been developed. These options consider the techniques and technologies required to address each stage of the lifecycle, such as segregation, treatment, recycle, and ultimate disposal in a radioactive waste repository, providing a toolbox to aid operators and regulators to determine the most appropriate management strategy. It is noted that national waste management programs currently have, or are in the process of developing, respective approaches to irradiated graphite management. The output of the Treatment and Disposal of Irradiated Graphite and other Carbonaceous Waste project is intended to aid these considerations, rather than dictate them.

• Steel and Composite Structures
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• 제19권1호
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• pp.93-110
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• 2015

The thermomechanical bending response of anti-symmetric cross-ply composite plates is investigated by the use of the simple four variable sinusoidal plate theory. The theory accounts for sinusoidal distribution of transverse shear stress, and satisfies the free transverse shear stress conditions on the top and bottom surfaces of the plate without using shear correction factor. By dividing the transverse displacement into bending and shear parts, the number of unknowns and governing equations for the present theory is reduced, significantly facilitating engineering analysis. The validity of the present theory is demonstrated by comparison with solutions available in the literature. Numerical results are presented to demonstrate the behavior of the system. The influences of aspect ratio, side-to-thickness ratio, thermal expansion coefficients ratio and stacking sequence on the thermally induced response are studied. The present study is relevant to aerospace, chemical process and nuclear engineering structures which may be subjected to intense thermal loads.

• Nuclear Engineering and Technology
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• 제56권5호
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• pp.1553-1561
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• 2024

Nondestructive radiography using cosmic ray muons has been used for decades to monitor nuclear reactor and spent nuclear fuel storage. Because nuclear fuel assemblies are highly dense and large, typical radiation probes such as x-rays cannot penetrate these target imaging objects. Although cosmic ray muons are highly penetrative for nuclear fuels as a result of their relatively high energy, the wide application of muon tomography is limited because of naturally low cosmic ray muon flux. This work presents a new image reconstruction algorithm to maximize the utility of cosmic ray muon in tomography applications. Muon momentum information is used to improve imaging resolution, as well as muon scattering angle. In this work, a new convolution was introduced known as M-value, which is a mathematical integration of two measured quantities: scattering angle and momentum. It captures the objects' quantity and density in a way that is easy to use with image reconstruction algorithms. The results demonstrate how to reconstruct images when muon momentum measurements are included in a typical muon scattering tomography algorithm. Using M-value improves muon tomography image resolution by replacing the scattering angle value without increasing computation costs. This new algorithm is projected to be a standard nondestructive radiography technique for spent nuclear fuel and nuclear material management.

• Journal of Radiation Protection and Research
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• 제39권1호
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• pp.54-60
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• 2014

IAEA는 핵물질 계량 관리 검사를 위해 다양한 방사선 검출기를 사용하고 있다. 주로 HPGe, NaI(Tl), CZT 등이 사용되며, 정확한 측정이 요구되는 검사에는 고분해능 HPGe 검출기 활용도가 높다. HPGe 검출기는 추가적인 냉각장치로 인하여 부피가 크고 무거우며, 사용하기 전에 충분히 냉각시켜야 하기 때문에 측정의 준비 시간이 많이 걸린다는 단점이 있다. 이러한 문제점을 해결하기 위해 가볍고 짧은 사용 전 냉각이 요구되는 휴대형 HPGe가 개발되었다. 본 논문은 개발된 휴대형 HPGe 검출기 시제품을 실제 IAEA 사찰 현장에 적용하여 얻은 성능평가 결과를 기술한다. 휴대형 HPGe로 얻은 방사선 스펙트럼은 핵물질 종류와 농축도에 따라 다른 특징을 보였고, 또한 $^{235}U$과 $^{238}U$의 붕괴 계열에서 방출되는 감마선 및 우라늄의 특성 x-선 차이도 확인할 수 있었다. 그리고 휴대형 HPGe 검출기 시제품으로 측정한 농축도는 핵물질 종류에 따라 실제값과 9 ~ 27%의 상대적 오차를 보였다. 휴대형이라는 소형 검출기의 한계 때문에 일부 핵물질은 IAEA에서 요구하는 정확도를 만족시키지 못하는 경우도 있었지만 향후 추가적인 연구의 수행으로 이러한 문제점은 해결 가능할 것으로 판단된다. 본 논문은 새로운 휴대형 HPGe 검출기를 안전조치에 적용한 사례와 측정한 스펙트럼을 농축도 분석 코드로 분석한 결과를 다룬다. 따라서 국내 원자력시설의 우라늄 농축도 검증을 위한 IAEA 안전조치 사찰 결과를 분석한 논문이 별로 발표되지 않은 상황에서, 본 논문은 안전조치 검사 결과 분석에도 유익할 것으로 판단된다. 개발된 방사선 검출기의 개선 사항도 함께 논의하였으므로 향후 관련 분야 방사선 검출기 개발에도 기여할 것으로 예상된다.

• 핵의학기술
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• 제19권1호
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• pp.44-50
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• 2015

Purpose Quality control used in laboratory help to sustain precision and accuracy consistently to ensure the Diagnostic and treatment for medical employee. To perform an evaluation in statistical manner, it is recommended to use different quality control material than calibrator from manufacturer, quality control material must include analyzed concentration perimeter, must use more than two different concentration materials and recommended to use materials to indicate the concentration in clinical use. However, currently used quality control material has limit of evaluation due to unconsidered concentration or improperly used to get clinical importance data. Therefore, we compared the value of quality control, DIACON Hormone Level 1, 2, 3 (Scantibodies, USA) and DIACON Tumor Level 1, 2, 3 which applied to clinical concentration range. Materials and Methods DIACON Hormone Level 1, 2, 3 (Scantibodies, USA) and DIACON Tumor Level 1, 2, 3 (Scantibodies, USA) that used materials and methods test to compare the result from five RIA testing institution and one institution that used Elecsys (ROCHE) and Architect (ABOTT) for each level. The reagent RIA kit that used in this experiment is followed by Table 2 and 3. Test has performed by instruction itself and follow by instruction. Results Among DIACON hormone result of twenty four items, level 1 have three items, level 2 have four items and level 3 have five items were out of manufacturer set up range based on the average value. Among DIACON tumor result of thirteen items, level 1 have three items, level 2 have four items and level 3 have five items were out of manufacturer set up range. Other result were inside of manufacturer range. Conclusion For quality control material, it is widely available in market, but it is limited for normal range which is only concerned in improper clinical value and difficult to evaluate important concentration area in terms of clinical analyze. In this experiment, we evaluate Hormone twenty three items and Tumor thirteen items with DIACON Hormone and Tumor (Scantibodies, USA) to resolve this limit and we could observe that it ca be substituted and used.