• Proceedings of the Safety Management and Science Conference
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• 2011.11a
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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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• v.49 no.5
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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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• v.19 no.1
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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.

• Journal of Radiation Protection and Research
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• v.39 no.1
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• pp.54-60
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• 2014

IAEA has employed various types of radiation detectors - HPGe, NaI, CZT - for accountancy of nuclear material. Among them, HPGe has been mainly used in verification activities required for high accuracy. Due to its essential cooling component(a liquid-nitrogen cooling or a mechanical cooling system), it is large and heavy and needs long cooling time before use. New hand-held portable HPGe has been developed to address such problems. This paper deals with results of performance evaluation test of the new hand-held portable HPGe prototype which was used during IAEA's inspection activities. Radioactive spectra obtained with the new portable HPGe showed different characteristics depending on types and enrichments of nuclear materials inspected. Also, Gamma-rays from daughter radioisotopes in the decay series of $^{235}U$ and $^{238}U$ and characteristic x-rays from uranium were able to be remarkably separated from other peaks in the spectra. A relative error of enrichment measured by the new portable HPGe was in the range of 9 to 27%. The enrichment measurement results didn't meet partially requirement of IAEA because of a small size of a radiation sensing material. This problem might be solved through a further study. This paper discusses how to determine enrichment of nuclear material as well as how to apply the new hand-held portable HPGe to safeguard inspection. There have been few papers to deal with IAEA inspection activity in Korea to verify accountancy of nuclear material in national nuclear facilities. This paper would contribute to analyzing results of safeguards inspection. Also, it is expected that things discussed about further improvement of a radiation detector would make contribution to development of a radiation detector in the related field.

• The Korean Journal of Nuclear Medicine Technology
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• v.19 no.1
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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.