• Journal of the Korean Society of Safety
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• v.31 no.3
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• pp.96-101
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• 2016

Previous literature has been investigated various aspects of accident occurrence and prevention in construction field. However, those studied were limited in that they only focused on the death accident without considering the loss time accident. Based on this, the goal of current study was to investigate the nature of the loss time accident, and compare the results with the death accident. Results showed that 1) the occurrence rate of death accident was significantly higher in the form work, temporary work, and steel frame work; 2) the temporary work showed significantly higher occurrence rate of the loss time accident and the death accident as compared to others; 3) ratio of the loss time accident to the death accident in domestic construction field was 50:1; 4) fall accident showed biggest occurrence rate in both the loss time accident and the death accident; and 5) more that 80% of workers in both the loss time accident and the death accident was between 41 and 65 years old.

• Journal of the Korean Society of Safety
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• v.32 no.5
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• pp.96-102
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• 2017

The highest fatal accident ratio was recorded in the construction industry. According to the industrial insurance premium rate & business type example, among the construction industry, the architectural work has the highest fatal and loss time accident ratio. Previous literature has investigated various aspects of accident occurrence and prevention in architectural work. However, those studied were limited in that they only focused on the fatal accident without considering the loss time accident. But non fatal accidents were recorded more than 50 times of fatal accidents. Therefore non fatal accidents must be controlled to lessen industrial accidents. Based on this, the goal of this study was to investigate the nature of the loss time accident and derive the risk index of work type in architectural work. In this study, opinions of safety experts were gathered and the risk index of work type was derived using AHP(Analytic Hierarchy Process). And verification was accomplished by comparing the results of this study with the risk index derived by analysis of accident records. Results showed that the risk index of work type was significantly higher in steel frame work, temporary installation work, earth & foundation work, facilities work, concrete work. And statistical analysis for verification showed that coefficient of Pearson correlation was 0.686 and P-value was 0.001.

• Journal of Korean Society of Industrial and Systems Engineering
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• v.19 no.39
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• pp.99-116
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• 1996

The production activity by human is accompanied by various accidents, resulting in human and property loss. If information on these industrial accident can be collected, organized and analyzed for a period of time and be used in the decision-making process for the purpose of preventing industrial accident, we will be able to get rid of industrial accident and prevent human and property loss and creat a pleasant industrial atmosphere. In order to achieve this goal, the collected information should be accurate, and trusted in the work place or government agency the information is being utilized. This research analyzed the problem in our nation's industrial accident statistics and estimated the number of accidents that are occurring and suggested improvement measures so that the industrial accident statistics can be calculated accurately.

• Nuclear Engineering and Technology
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• v.47 no.1
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• pp.74-84
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• 2015

If a transient occurs in a nuclear power plant (NPP), operators will try to protect the NPP by estimating the kind of abnormality and mitigating it based on recommended procedures. Similarly, operators take actions based on severe accident management guidelines when there is the possibility of a severe accident occurrence in an NPP. In any such situation, information about the occurrence time of severe accident-related events can be very important to operators to set up severe accident management strategies. Therefore, support systems that can quickly provide this kind of information will be very useful when operators try to manage severe accidents. In this research, the occurrence times of several events that could happen during a severe accident were predicted using support vector machines with short time variations of plant status variables inputs. For the preliminary step, the break location and size of a loss of coolant accident (LOCA) were identified. Training and testing data sets were obtained using the MAAP5 code. The results show that the proposed algorithm can correctly classify the break location of the LOCA and can estimate the break size of the LOCA very accurately. In addition, the occurrence times of severe accident major events were predicted under various severe accident paths, with reasonable error. With these results, it is expected that it will be possible to apply the proposed algorithm to real NPPs because the algorithm uses only the early phase data after the reactor SCRAM, which can be obtained accurately for accident simulations.

• Proceedings of the ESK Conference
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• 1995.10a
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• pp.114-124
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• 1995

The production activity by human is accompanied by various accidents, resulting in human and property loss. If information on these industrial accident can be collected, organized and analyzed for a period of time and be used in the decision-making process for the purpose of preventing industriar accident, we will be able to get rid of industriar accident and prevent human and property loss and creat a pleasant industrial atmosphere. In order to achieve this goal, the collected information should be accurate, and trusted in the work place or govemement agency the informantion is being utilized. This research analyzed the problem in our nation's industrial accident statistics and estimated the number of accidents that are occuring and suggested improvement measures so that the industrial accident statistics can be calculated arately.

• Nuclear Engineering and Technology
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• v.53 no.2
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• pp.484-497
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• 2021

This paper proposes an extended time uncertainty analysis approach in Level 2 human reliability analysis (HRA) considering severe accident management (SAM) strategies. The method is a time-based model that classifies two time distribution functions-time required and time available-to calculate human failure probabilities from delayed action when implementing SAM strategies. The time required function can be obtained by the combination of four time factors: 1) time for diagnosis and decision by the technical support center (TSC) for a given strategy, 2) time for strategy implementation mainly by the local emergency response organization (ERO), 3) time to verify the effectiveness of the strategy and 4) time for portable equipment transport and installation. This function can vary depending on the given scenario and includes a summation of lognormal distributions and a choice regarding shifting the distribution. The time available function can be obtained via thermal-hydraulic code simulation (MAAP 5.03). The proposed approach was applied to assess SAM strategies that use portable equipment and safety depressurization system valves in a total loss of component cooling water event that could cause reactor vessel failure. The results from the proposed method are more realistic (i.e., not conservative) than other existing methods in evaluating SAM strategies involving the use of portable equipment.

• Journal of the Korean Society of Safety
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• v.36 no.3
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• pp.74-80
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• 2021

Korea Atomic Energy Research Institute (KAERI) has been operating an integral effects test facility, the Advanced Thermal-Hydraulic Test Loop for Accident Simulation (ATLAS), according to APR1400 for transient experimental and design basis accident simulation. Moreover, based on the experimental data, the domestic standard problem (DSP) program has been conducted in Korea to validate system codes. Recently, through DSP-05, the performance of the passive auxiliary feedwater system (PAFS) in the event of multiple steam generator tube rupture (MSGTR) has been analyzed. However, some errors exist in the reference input model distributed for DSP-05. Furthermore, the calculation results of the heat loss correlation for the secondary system presented in the technical report of the reference indicate that a large difference is present in heat loss from the target value. Thus, in this study, the reference model is corrected using the geometric information from the design report and drawings of ATLAS. Additionally, a new heat loss correlation is suggested by fitting the results of the heat loss tests. Herein, MSGTR-PAFS accident analysis is performed using MARS-KS 1.5 with the improved model. The steady-state calculation results do not significantly differ from the experimental values, and the overall physical behavior of the transient state is properly predicted. Particularly, the predicted operating time of PAFS is similar to the experimental results obtained by the modified model. Furthermore, the operating time of PAFS varies according to the heat loss of the secondary system, and the sensitivity analysis results for the heat loss of the secondary system are presented.

• Journal of the Korean Society of Safety
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• v.32 no.4
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• pp.73-78
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• 2017

In this study, the risk level of architectural works was calculated by applying work period and number of input workers based on accidents records from 2012 to 2014 and the architectural works were divided into four groups(High-High, High-Low, Low-High, Low-Low) according to risk levels of fatal accidents and loss time accidents. And then questionnaire on the job stress level of workers was performed for 670 workers working in the architectural work using Korean Occupational Stress Questionnaire Form developed by KOSHA. And then the relationship between the risk level and job stress level of four groups was analyzed. Results showed that 1) risk levels of fatal and loss time accidents applied by work period and input workers were analyzed to be different with those of previous research based on the number of fatal and loss time accidents; 2) job stress level of workers has been analyzed to have a significant relationship with the risk level of fatal and loss time accident; 3) specially, the average of job stress level of 'HH(High-High)' group was higher than those of other groups; 4) among the subfactors of job stress, interpersonal conflict, job insecurity, organizational system and lack of reward were analyzed to be key factors to affect the risk level.

• Nuclear Engineering and Technology
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• v.50 no.4
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• pp.582-588
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• 2018

Accident diagnosis is one of the complex tasks for nuclear power plant (NPP) operators. In abnormal or emergency situations, the diagnostic activity of the NPP states is burdensome though necessary. Numerous computer-based methods and operator support systems have been suggested to address this problem. Among them, the recurrent neural network (RNN) has performed well at analyzing time series data. This study proposes an algorithm for accident diagnosis using long short-term memory (LSTM), which is a kind of RNN, which improves the limitation for time reflection. The algorithm consists of preprocessing, the LSTM network, and postprocessing. In the LSTM-based algorithm, preprocessed input variables are calculated to output the accident diagnosis results. The outputs are also postprocessed using softmax to determine the ranking of accident diagnosis results with probabilities. This algorithm was trained using a compact nuclear simulator for several accidents: a loss of coolant accident, a steam generator tube rupture, and a main steam line break. The trained algorithm was also tested to demonstrate the feasibility of diagnosing NPP accidents.

• Nuclear Engineering and Technology
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• v.53 no.2
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• pp.474-483
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• 2021

To establish the exclusive role of hydrogen on burst behaviour of Zircaloy-4 during loss-of-coolant accident transients, an extensive single-rod burst tests were conducted on both unirradiated as-received and hydrogenated Zircaloy-4 cladding tubes at different heating rates and internal overpressures. The visual observations of cladding tubes during bursting as well as post-burst are presented in detail to understand the effect of hydrogen concentration, heating rate, and internal pressure. Impact of hydrogen on burst parameters-burst stress, burst strain, burst temperature-during loss-of-coolant accident transients are compared and discussed. Rupture at multiple locations for hydrogenated cladding at lower internal pressure and higher heating rate is reported for the very first time. A novel burst criterion accounting hydrogen concentration in nuclear fuel cladding is proposed.