• Nuclear Engineering and Technology
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• v.25 no.1
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• pp.102-109
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• 1993

A PC-computer program RADAP has been developed in this study to perform a quick real-time analysis of dose assessment following an accident in a nuclear facility. RADAP uses an interactive LKagrangian puff model in simulating the transport and diffusion of radioactive plume in the atmosphere. For real-time analysis, RADAP treats one or multiple puffs of ground-level releases, simultaneously. It is assumed to maintain a Gaussian distribution within the puff and the diffusion coefficients are computed using the USNRC's normal sigma curve method. The program, however, does not consider the spatial variations but the temporal variations in wind conditions. Whole body and thyroid doses for 3$\times$31 grid are directed to output files, and they are also displayed through computer graphics on VGA or EGA color monitor. The results show that RADAP can be an excellent tool for quick estimation of accidental doses.

• Nuclear Engineering and Technology
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• v.55 no.6
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• pp.2026-2033
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• 2023

Due to Thailand's nuclear energy public acceptance problem, the understanding of nuclear energy public perception was the key factor affecting to re-consideration of the nuclear energy program. Thailand Institute of Nuclear Technology and its alliances together developed the classification model for the nuclear energy public perception from the big data comments on social media using Facebook using deep transfer learning. The objective was to insight into the Thailand nuclear energy public perception on Facebook social media platform using sentiment analysis. The supervised learning was used to generate up-to-date classification model with more than 80% accuracy to classify the public perception on nuclear power plant news on Facebook from 2009 to 2022. The majority of neutral sentiments (80%) represented the opportunity for Thailand to convince people to receive a better nuclear perception. Negative sentiments (14%) showed support for other alternative energies due to nuclear accident concerns while positive sentiments (6%) expressed support for innovative nuclear technologies.

• Journal of the Korean Institute of Illuminating and Electrical Installation Engineers
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• v.24 no.4
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• pp.116-122
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• 2010

This paper describes the up-grade of the turbine governor for steam turbine due to its poor operation from long time use. The analog type governor of the unit 1 in Kori nuclear power plant in Korea was removed and the new digital type turbine governor was developed and installed. The procedure for the actual application, site adaptability test using dynamic simulator and the result of actual operation are described here. And the program for nuclear steam turbine is suggested here.

• Proceedings of the Korea Society for Simulation Conference
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• 2004.05a
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• pp.94-100
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• 2004

KEPRI has developed an Nuclear Steam Supply System(NSSS) thermal-hydraulic simulation program (called ARTS-KORIl) based on the best-estimate system code, RETRAN, as a part of the development project for the KORI unit 1 nuclear power plant simulator. To develop the RETRAN code as an NSSS T/H engine for the simulator, a number of code modifications, such as simplifications and removing of discontinuities of the physical correlations, were made to satisfy the simulator requirements of robustness and real time calculation capability Some simplified models and a backup system were also developed to simulate some transients that cannot be efficiently calculated by the RETRAN part of ARTS-KORIl.

• Journal of the Korean Society of Safety
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• v.26 no.2
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• pp.6-12
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• 2011

The failure probabilities of pipes in nuclear power plants due to stress corrosion are obtained using the P-PIE program, which is developed for evaluating failure probability of pipes based on the existing PRAISE program. Leak, big leak and LOCA(loss of coolant accident) probabilities are calculated as a function of operating time for several pipes in a domestic nuclear plant. The sensitivity analysis is also performed to find out the important parameters for the failure of pipes due to stress corrosion. The results show that the steady state oxygen concentration and steady state temperature are important parameters and failure probability is very low when the oxygen concentration is maintained according to the regulation.

• Nuclear Engineering and Technology
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• v.30 no.4
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• pp.308-317
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• 1998

Ensuring occupational radiation exposure(ORE) as low as is reasonably achievable(ALARA) has been one of very important requirements in a nuclear power plant. It is well known that about 70 percent of occupational dose has incurred from maintenance jobs in the outage period. To reduce occupational dose effectively, the high-dose jobs in the outage period should be identified with their dose reduction potentials and methods. In this study, a PC-based ORE database program, INSTORE, is developed to evaluate ORE doses in individual jobs, and the ORE data of Kori Units 3 and 4 are assembled to the database. Based on customary job classification, radiation work is classified into 26 main jobs which comprise 61 detailed jobs, and occupational doses are assessed according to each detailed job. As a result, high-dose jobs are identified with dose reduction priority in terms of collective ORE dose. It is recommended that adeqaute dose reduction methods for these jobs should be prepared to improve their working conditions and procedures.

• Nuclear Medicine and Molecular Imaging
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• v.41 no.2
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• pp.78-84
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• 2007

Quantitative analysis of dynamic brain PET data using a tracer kinetic modeling has played important roles in the investigation of functional and molecular basis of various brain diseases. Parametric imaging of the kinetic parameters (voxel-wise representation of the estimated parameters) has several advantages over the conventional approaches using region of interest (ROI). Therefore, several strategies have been suggested to generate the parametric images with a minimal bias and variability in the parameter estimation. In this paper, we will review the several approaches for parametric imaging with linearized methods which include graphical analysis and mulilinear regression analysis.

• Nuclear Engineering and Technology
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• v.28 no.3
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• pp.331-338
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• 1996

In the thermal-hydraulic design, the effect of fuel rod bow is quantified tv the rod bow DNBR penalty which is a key design parameter to assure the coolability of fuel assembly in the pressurized water reactor. In this work, a computer program for the evaluation of the rod bow DNBR penalty based on Westinghouse methodology is developed and its application procedure is proposed. The computer simulation is based on the Monte-Carlo method. The qualification of developed computer program is performed by a comparison of calculational result with that given by Westinghouse's document. A new application procedure is built using batch mean and batch standard deviation. The normality of sample population generated by the batch calculation is confirmed by means of a chi-square test for goodness of fit. On the view point of statistics it is effected that the more reliable design value may be produced by the new application procedure.

• Nuclear Engineering and Technology
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• v.55 no.4
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• pp.1439-1447
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• 2023

The fuel cycle characteristics of the IVG.1M reactor were studied within the framework of the research reactor conversion program to modernize the IVG.1M reactor. Optimum use of the nuclear fuel and reactor was achieved through routine methods which included partial fuel reloading combined with scheduled maintenance operations. Since, the additional problem in planning the fuel cycle of the IVG.1M reactor was the poisoning of the beryllium parts of the core, reflector, and control system. An assessment of the residual power and composition of spent fuel is necessary for the selection and justification of the technology for its subsequent management. Computational studies were performed using the MCNP6.1 program and the neutronics model of the IVG.1M reactor. The proposed scheme of annual partial fuel reloading allows for maintaining a high reactor reactivity margin, stabilizing it within 2-4 β_eff for 20 years, and achieving a burnup of 9.9-10.8 MW × day/kg U in the steady state mode of fuel reloading. Spent fuel immediately after unloading from the reactor can be placed in a transport packaging cask for shipping or safely stored in dry storage at the research reactor site.

• Journal of Nutrition and Health
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• v.44 no.4
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• pp.292-302
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• 2011

Adipocytokines (adiponectin, leptin and resistin) are known to play a major role in development of cardiovascular disease (CVD) and intervention program is effective in reducing CVD risk factors. However, intervention program to improve the CVD risk factors including adipocytokines has been less studied. This study investigated the effects of 12-weeks worksite intervention program on cardiovascular risk factors, adipocytokines and nutrients intakes in industrial workers. 157 industrial male workers (32 metabolic syndrome (MS) subjects, 125 healthy subjects using age-matched stratified random sampling) received 5 face-to-face counseling based on their health profiles. Anthropometry, biochemical parameters and nutrients intakes were measured. The diagnosis of MS was adapted from modified NCEP-ATP III criteria (2001) and Asia-Pacific definition criteria (2000) for waist circumference (WC). After the intervention program, WC, BMI, SBP, insulin, leptin and intakes of total energy and fiber were significantly decreased (p < 0.05), while adiponectin was significantly increased (p < 0.05) in MS subjects. The WC, BMI, SBP, total cholesterol, LDL and HDL-cholesterol, HbA1c, leptin and intakes of total energy, protein and fat were significantly decreased (p < 0.05) and adiponectin was significantly increased (p < 0.05) in normal subjects. Multiple linear regression revealed that adiponectin was positively correlated with HDL-cholesterol (p < 0.01). Leptin was positively correlated with WC (p < 0.01), and resistin was positively correlated with HbA1c (p < 0.05) and intakes of total energy (p < 0.05), and negatively correlated with HDL-cholesterol (p < 0.05). The results of the 12 weeks intervention showed a positive impact on adipocytokines and nutrients intakes of industrial workers to reduce cardiovascular risk factors. Further research is needed to verify a tailored long-term worksite intervention program including adipocytokines as a protective factor for the CVD.