• Title/Summary/Keyword: atomic data

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A System Design for The Tomographical Assay

  • Lee, Yong-Deok;Na, Won-Woo;Kim, Ho-Dong;Hong, Jong-Sook
    • Proceedings of the Korean Nuclear Society Conference
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    • 1996.05c
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    • pp.397-402
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    • 1996
  • A remote operational system for the tomographical assay was designed to scan the sample and to assay the inside radioactive materials distribution three dimensionally, composed of 3 axes moving table, collimator, data acquisition system in a PC control. The system design was done by considering that how the accurate assay be affected by the modeling or by the other system components. In the system design, MCNP code simulation was done to find the optimum condition for the spatial assay of the radioactive materials.

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DEVELOPMENT OF DESKTOP SEVERE ACCIDENT TRAINING SIMULATOR

  • Kim, Ko-Ryuh;Park, Soo-Yong;Song, Yong-Mann;Ahn, Kwang-Il
    • Nuclear Engineering and Technology
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    • v.42 no.2
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    • pp.151-162
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    • 2010
  • A severe accident training simulator that can simulate important severe accident phenomena and nuclear plant behaviors is developed. The simulator also provides several interactive control devices, which are helpful to assess results of a particular accident management behavior. A simple and direct dynamic linked library (DLL) data communication method is used for the development of the simulator. Using the DLL method, various control devices were implemented to provide an interactive control function during simulation. Finally, a training model is suggested for accident mitigation training and its performance is verified through application runs.

Evaluation of thermal striping damage for a tee-junction of LMR secondary piping”

  • Lee, Hyeong-Yeon;Kim, Jong-Bum;Bong Yoo;Yoon, Sam-Son
    • Proceedings of the Korean Nuclear Society Conference
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    • 1998.05b
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    • pp.837-843
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    • 1998
  • This paper presents the thermomechanical and fracture mechanics evaluation procedure of thermal striping damage on the secondary piping of LMFR using Green's function method and standard FEM. The thermohydraulic loading conditions used in the present analysis are simplified sinusoidal thermal loads and the random type data thermal load. The thermomechainical fatigue damage was evaluated according to ASME code subsectionNH. The analysis results of fatigue for the sinusoidal and random load cases show that fatigue failure would occur at a geometrically discontinuous location during 90,000 hours of operation The fracture mechanics analysis showed that the crack would be initiated at an early stage of the operation. The fatigue crack was evaluated to propagate up to 5 ㎜ along the thickness direction during the first 944 and 1083 hours of operation for the sinusoidal and the random loading cases, respectively.

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A Study on LAN Applications in Nuclear Safety System

  • Kim, Sung;Lee, Young-Ryul;Koo, Jun-Mo;Han, Jae-Bok
    • Proceedings of the Korean Nuclear Society Conference
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    • 1995.10a
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    • pp.166-172
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    • 1995
  • It is a general tendency to digitalize the conventional relay based I&C systems in nuclear power plant. But, the digitalization of nuclear safety systems has many a difficulty to surmount. The typical on thing of many difficulties is the data communication problem between local controllers and systems. The network architecture built with LAN(Local Area Network) in digital systems of the other industries are general. But in case of nuclear safety systems many considerations in point of safety and license are required to implement it in the field. In this paper, some considerations for applying LAN in nuclear safety systems were reviewed.

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Corrosion model for Zircaloy-4 Cladding in PWR

  • Lee, Byung-Ho;Yoo, Yeon-Jong;Kook, Yang-Hyun;Sohn, Dong-Seong
    • Proceedings of the Korean Nuclear Society Conference
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    • 1999.05a
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    • pp.279-279
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    • 1999
  • To improve the corrosion model of the fuel performance analysis code COSMOS, a model was developed considering thermohydraulic phenomena and the effect of water chemistry and low Sn in the alloy composition on the corrosion behavior. It is assumed that the lithium enhancement factor influences the corrosion behavior only if the subcooled void is present in the coolant. The developed model was verified with the database obtained from Grohnde and Ringhals 3 reactors. Comparison of predicted oxide thickness with measured data showed the applicability of COSMOS code to analyze the cladding oxidation. In the future, the effect of the hydride in the cladding and the precipitate changes due to irradiation should be included.cluded.

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Multiple Scale Processes in Microstructural Evolution: Case Study of Self-Reinforced β-Si3N4

  • Becher, Paul F.
    • Journal of the Korean Ceramic Society
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    • v.53 no.6
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    • pp.575-580
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    • 2016
  • Microstructural design of ceramics has generally focused on information gathered at the micro- and macro-scales and related this to how specific properties could be improved. Ceramic processing serves as the key to optimizes the final microstructure. However, the advent of nano-scale microstructures and highly advanced characterization tools are forcing us to develop new knowledge of what is occurring not just at the micro-scale but also at the atomic level. Thus we are now beginning to be able to address how microstructure is influenced by events at the atomic scale using atomic scale images and data. Theoreticians have joined us in interpreting the mechanisms involved in the "microstructural" evolution at multiple scales and how this can be used to enhance specific properties of ceramics. The focus here is on delving into the various layers the "microstructure" in order understand how atomic-scale events influence the structure and properties of ceramics.

EVALUATION OF FAST NEUTRON FLUENCE FOR KORI UNIT 3 PRESSURE VESSEL

  • Yoo, Choon-Sung;Kim, Byoung-Chul;Chang, Kee-Ok;Lee, Sam-Lai;Park, Jong-Ho
    • Nuclear Engineering and Technology
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    • v.38 no.7
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    • pp.665-674
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    • 2006
  • Three-dimensional neutron flux and fluence of Kori Unit 3 were evaluated using the synthesis technique described in Regulatory Guide 1.190 for all reactor geometry. For this purpose DORT neutron transport calculations from Cycle 1 to Cycle 15 were performed using BUGLE-96 cross-section library. The calculated flux and fluence were validated by comparing the calculated reaction rates to the measurement data from the dosimetry sensor set of the $5^{th}$ surveillance capsule withdrawn at the end of cycle 15 of Kori Unit 3. And then the best estimation of the neutron exposures for the reactor vessel beltline region was performed using the least square evaluation. These results can be used in the assessment of the state of embrittlement of Kori Unit 3 pressure vessel.

Gene Expression Profiles Following High-Dose Exposure to Gamma Radiation in Salmonella enterica serovar Typhimurium

  • Lim, Sangyong;Jung, Sunwook;Joe, Minho;Kim, Dongho
    • Journal of Radiation Industry
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    • v.2 no.3
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    • pp.111-119
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    • 2008
  • Microarrays can measure the expression of thousands of genes to identify the changes in expression between different biological states. To survey the change of whole Salmonella genes after a relatively high dose of gamma radiation (1 kGy), transcriptome dynamics were examined in the cells by using DNA microarrays. At least 75 genes were induced and 89 genes were reduced two-fold or more after irradiation. Several genes located in pSLT plasmid, cyo operon, and Gifsy prophage were induced along with many genes encoding uncharacterized proteins.While, the expression of genes involved in the virulence of Salmonella as well as metabolic functions were decreased. Although the radiation response as a whole could not be illustrated by using DNA microarrays, the data suggest that the response to high dose of irradiation might be more complex than the SOS response.

An Experimental Study on Heat Transfer Characteristics Just Before Critical Heat Flux in Uniformly Heated Vertical Annulus Under a Wide Range of Pressures

  • Chun, Se-Young;Moon, Sang-Ki;Chung, Heung-June;Chung, Moon-Ki
    • Nuclear Engineering and Technology
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    • v.34 no.4
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    • pp.269-285
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    • 2002
  • Water heat transfer experiments were carried out in a uniformly heated annulus with a wide range of pressure conditions. The local heat transfer coefficients for saturated water (low boiling have been measured just before the occurrence of the critical heat flux (CHF) along the length of the heated section. The trends of the measured heat transfer coefficients were quite different from the conventional understanding for the heat transfer of saturated flow boiling. This discrepancy was explained from the nucleate boiling in the liquid film of annular flow under high heat flux conditions. The well-known correlations were compared with the measured heat transfer coefficients. The Shah and Kandlikar correlations gave better prediction than the Chen correlation. However, the modified Chen correlation proposed in the present work showed the best agreement with the present data among correlations examined .

Application of compressive sensing and variance considered machine to condition monitoring

  • Lee, Myung Jun;Jun, Jun Young;Park, Gyuhae;Kang, To;Han, Soon Woo
    • Smart Structures and Systems
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    • v.22 no.2
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    • pp.231-237
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    • 2018
  • A significant data problem is encountered with condition monitoring because the sensors need to measure vibration data at a continuous and sometimes high sampling rate. In this study, compressive sensing approaches for condition monitoring are proposed to demonstrate their efficiency in handling a large amount of data and to improve the damage detection capability of the current condition monitoring process. Compressive sensing is a novel sensing/sampling paradigm that takes much fewer data than traditional data sampling methods. This sensing paradigm is applied to condition monitoring with an improved machine learning algorithm in this study. For the experiments, a built-in rotating system was used, and all data were compressively sampled to obtain compressed data. The optimal signal features were then selected without the signal reconstruction process. For damage classification, we used the Variance Considered Machine, utilizing only the compressed data. The experimental results show that the proposed compressive sensing method could effectively improve the data processing speed and the accuracy of condition monitoring of rotating systems.