• Journal of computational fluids engineering
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• v.20 no.1
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• pp.84-91
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• 2015

SMART adopts, very unique facility, an FMHA to enhance the thermal and flow mixing capability in abnormal conditions of some steam generators or reactor coolant pumps. The FMHA is important for enhancing thermal mixing of the core inlet flow during a transient and even during accidents, and thus it is essential that the thermal mixing characteristics of flow of the FMHA be understood. Investigations for the mixing characteristics of the FMHA had been performed by using experimental and CFD methods in KAERI. In this study, the temperature distribution at the core inlet region is investigated for several abnormal conditions of steam generators using the commercial code, FLUENT 12. Simulations are carried out with two kinds of FMHA shapes, different mesh resolutions, turbulence models, and steam generator conditions. The CFD results show that the temperature deviation at the core inlet reduces greatly for all turbulence models and steam generator conditions tested here, and the effect of mesh refinement on the temperature distribution at the core inlet is negligible. Even though the uniformity of FMHA outlet hole flow increases the thermal mixing, the temperature deviation at the core inlet is within an acceptable range. We numerically confirmed that the FMHA applied in SMART has an excellent mixing capability and all simulation cases tested here satisfies the design requirement for FMHA thermal mixing capability.

• Journal of Advanced Navigation Technology
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• v.21 no.5
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• pp.491-500
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• 2017

This paper investigates a low cost dual modular redundancy system based on heartbeat which can be applied to traffic control signal system. Failure of the traffic control signal system can cause traffic confusion and traffic accidents. Therefore safety and reliability of traffic control should be secured using fault tolerance technology. To do this, we configured a redundant board using the open source hardware and the heartbeat technique of Linux HA. The function of the traffic signal control system was verified and the fault recovery time was measured using fault injection test. As a result of the test, the fault recovery time was confirmed to be less than 9 seconds on average, confirming that the reliability target time is satisfied. Based on the results of this study, it is expected that it can be applied to fields requiring high reliability systems such as aviation, space, and nuclear power embedded systems.

• Journal of the Korean Society for Railway
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• v.12 no.5
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• pp.744-750
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• 2009

According to the result of related studies, the degradation of human performance has been revealed as one of the most significant causes resulting in the safety of any human-involved system. This means that preventing the occurrence of accidents/incidents through avoiding the degradation of human performance is prerequisite for their successive operation. To this end, it is necessary to develop a plausible tool to evaluate the complexity of a task, which has been known as one of the decisive factors affecting the human performance. For this reason, in this paper, the complexity of tasks to be conducted by KTX drivers was quantified by TACOM measure that is enable to quantify the complexity of proceduralized tasks being used in nuclear power plants. After that, TACOM scores about the tasks of KTX drivers were compared with NASA-TLX scores that are responsible for the level of a subjective workload to be felt by KTX drivers.

• Journal of the Ergonomics Society of Korea
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• v.35 no.6
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• pp.473-492
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• 2016

Objective: This paper discusses the recent challenges to human factors engineering due to the safety culture. Background: As incidents occurring in specific fields such as logistics, plant, energy and medical sectors in Korea, as well as in the public sectors including railway, road, aviation and shipping, are recently raised as social issues from the disaster dimension, those incidents are dealt with as man-made disasters in many cases. The trend regarding all accidents as man-made disasters has been expanded in the active perspective that the controllability of all incidents should be ensured in technology development, due to change from a fatal point of view regarding disasters as random occurrence of uncertainties in the past. Method: Man-made disasters are concluded as human errors, and safety culture stands out as a cause of human errors or a new cause item recently. Because safety culture, however, is a very comprehensive term, of which true nature is obscure, although many definitions of safety culture have been presented, the safety culture may make avoid the true nature and responsibility of an incident, or make the main player and subject obscure. Raising safety culture as a cause without presenting a specific countermeasure will be just a wisdom of hindsight. Results and Conclusion: This study reviews the fundamental discussions on "Is safety culture a task of human factors engineering?" and the existing approach carried out from various perspectives in order to seek an effective approach on the new task of safety culture in the human factors engineering field. This study discusses an engineering approach to meet a precondition that safety culture is not just an added factor through a review of the approaches in the proactive fields such as nuclear power and aviation, and the traditional approaches of human factors engineering. Application: This study especially defines the perspective of socio-technological system that has expanded the existing man-machine system, and discusses a systemic approach embracing various interactions, and several overriding tasks.

• Journal of Radiation Protection and Research
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• v.39 no.2
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• pp.96-102
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• 2014

Urine bioassay has been widely used for internal dosimetry due to simple process of sampling and measurement. In this paper, we participated in the NRIP (NIST Radiochemistry Intercomparison Program) hosted by US NIST to carry out a reliable performance test of urine bioassay and introduced the measurement method and results of NRIP-2013. In customary exercise with 60 days of reporting time, bioassay results of 12 radionuclides in the synthetic urine samples were acceptable based on the performance criteria of ANSI N13.30. In emergency preparedness exercise with 8 hours of reporting time, bioassay results of 9 radionuclides showed that differences ranged from -35% to 45%. However, we concluded that urine bioassay applied for emergency preparedness exercise would be applicable for rapid screening and estimation of internal exposure within a difference of ${\pm}45%$ in the event of radiological accidents.

• Journal of Radiation Protection and Research
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• v.26 no.4
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• pp.433-440
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• 2001

Using the different procedures suggested by the recognized organizations including IAEA, FDA, WHO and CED, derived Intervention levels (DILs) against contamination of foodstuffs were evaluated for considerations in radiological emergency planning in Korea. Three radionuclides important in terms of the consequence due to accidents at a nuclear power plant, i.e., $^{137}Cs,\;^{90}Sr$ and $^{131}I$, were considered. Intervention level for dose based on new recommendation of the ICRP (ICRP-60) was applied. The DILs tot the same foodstuff differ by up to afactor of 10. In most cases, the DILs based on FDA and WHO approaches were more conservative than those based on IAEA and CEC approaches. A critical age group for milk was infant of 3 month for all radionuclides. In most foods except milk, a critical age group was adult, 15yr and 5yr for $^{137}Cs,\;^{90}Sr$ and $^{131}I$, respectively.

• Journal of the Korea Institute of Information and Communication Engineering
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• v.19 no.2
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• pp.486-492
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• 2015

Radiation source imaging system is essential for protecting of radiation leakage accidents and minimizing damages from the radioactive materials, and is expected to play an important role in the nuclear plant decommissioning area. In this study, the stereoscopic camera principle was applied to develop a new radiation imaging device technology that can extract the radiation three-dimensional position information. This radiation three-dimensional imaging device (K3-RIS) was designed as a compact structure consisting of a radiation sensor, a CCD camera, and a pan-tilt only. It features the acquisition of stereoscopic radiation images by position change control, high-resolution detection by continuous scan mode control, and stereoscopic image signal processing. The performance analysis test of K3-RIS was conducted for a gamma-ray source(Cs-137) in radiation calibration facility. The test result showed that a performance error with less than 3% regardless of distances of the objects.

• Progress in Medical Physics
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• v.29 no.4
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• pp.123-136
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• 2018

The complex dose distribution and dose transfer characteristics of intensity-modulated radiotherapy increase the importance of precise beam data measurement and review in the acceptance inspection and preparation stages. In this study, we propose a process map for the introduction and installation of high-precision radiotherapy devices and present items and guidelines for risk management at the acceptance test procedure (ATP) and commissioning stages. Based on the ATP of the Varian and Elekta linear accelerators, the ATP items were checked step by step and compared with the quality assurance (QA) test items of the AAPM TG-142 described for the medical accelerator QA. Based on the commissioning procedure, dose quality control protocol, and mechanical quality control protocol presented at international conferences, step-by-step check items and commissioning guidelines were derived. The risk management items at each stage were (1) 21 ionization chamber performance test items and 9 electrometer, cable, and connector inspection items related to the dosimetry system; (2) 34 mechanical and dose-checking items during ATP, 22 multileaf collimator (MLC) items, and 36 imaging system items; and (3) 28 items in the measurement preparation stage and 32 items in the measurement stage after commissioning. Because the items presented in these guidelines are limited in terms of special treatment, items and practitioners can be modified to reflect the clinical needs of the institution. During the system installation, it is recommended that at least two clinically qualified medical physicists (CQMP) perform a double check in compliance with the two-person rule. We expect that this result will be useful as a radiation safety management tool that can prevent radiation accidents at each stage during the introduction of radiotherapy and the system installation process.

• Transactions of the Korean Society of Pressure Vessels and Piping
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• v.14 no.2
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• pp.1-10
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• 2018

Structures, systems and components of nuclear power plants should be able to maintain safety even in the event of design-basis accidents such as high-energy line breaks. The high-pressure steam jet ejected from the broken pipe may cause damage to the adjacent structures. The ANSI/ANS 58.2 code has been adopted as a technical standard for evaluating the jet impingement load. Recently, the U.S. NRC pointed out the non-conservativeness of the ANSI/ANS 58.2, because it does not take into account the blast wave effect, dynamic behavior of the jet, and oversimplifies the shape and load characteristics of the supersonic steam jet. Therefore, it is necessary to improve the evaluation method for the high-energy line break accident. In order to evaluate the behavior of supersonic steam jet, an appropriate numerical analysis technique considering compressible flow effect is needed. In this study, numerical analysis methodology for evaluating supersonic jet impingement load was developed and verified. In addition, the conservativeness of the ANSI/ANS 58.2 model was investigated using the numerical analysis methodology. It is estimated that the ANSI jet model does not sufficiently reflect the physical behavior of under-expanded supersonic steam jet and evaluates the jet impingement load lower than CFD analysis result at certain positions.

• Journal of radiological science and technology
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• v.42 no.5
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• pp.379-385
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• 2019

Radiation is used for various purposes such as cancer therapy, research of industrial and drugs. However, in case of radiation accidents such as terrorism, collapsing nuclear plant by natural disasters like Fukushima in 2011, very high radiation does expose to human and could lead to death. For this reason, many people are concerning about radiation exposures. Therefore, assessment and research of retrospective radiation dose to human by various path is an necessary task to be continuously developed. Radiation exposure for workers in radiation fields can be generally measured using a personal exposure dosimeter such as TLD, OSLD. However, general people can't be measured radiation doses when they are exposed to radiation. And even if radiation fields workers, when they do not in possession personal dosimeter, they also can't be measured exposure dose immediately. In this study, we conduct retrospective research on reconstruction of dose after exposure by using smart chip card of personal items through Optically Stimulated Luminescence (OSL). The OSL signal of smart chip card shows linear response from 0.06 Gy to 15 Gy and results of fading rate 45 %, 48% for 24 and 48 hours due to the natural emission of radiation in sample, respectively. The minimum detectable limit (MDD) was 0.38 mGy. This values are expected to use as correction values for reconstruction of exposure dose.