• Nuclear Engineering and Technology
• /
• v.55 no.8
• /
• pp.2723-2733
• /
• 2023

Transuranic nuclides (such as ²³⁸Pu, ²⁵²Cf, ²⁴⁹Bk, etc.) have a wide range of application in industry, medicine, agriculture, and other fields. However, due to the complex conversion chain and remarkable fission losses in the process of transuranic nuclides production, the generation amounts are extremely low. High flux reactor with high neutron flux and flexible irradiation channels, is regarded as the promising candidate for producing transuranic nuclides. It is of great significance to increase the conversion ratio of transuranic nuclides, resulting in higher efficiency and better economy. In this paper, we perform an optimization design evaluation of producing transuranic nuclides in high flux reactor, which includes optimization design of irradiation target and influence study of reactor core loading. It is demonstrated that the production rate increases with appropriately determined target material and target structure. The target loading scheme in the irradiation channel also has a significant influence on the production of transuranic nuclides.

• Nuclear Engineering and Technology
• /
• v.45 no.2
• /
• pp.179-190
• /
• 2013

A station blackout experiment called SBO-01 was performed at the ATLAS facility. From the SBO-01 test, the station blackout scenario can be characterized into two typical phases: A first phase characterized by decay heat removal through secondary safety valves until the SG dryouts, and a second phase characterized by an energy release through a blowdown of the primary system after the SG dryouts. During the second phase, some physical phenomena of the change over a pressurizer function, i.e., the pressurizer being full before the POSRV $1^{st}$ opening and then its function being taken by the RV, and the termination of normal natural circulation flow were identified. Finally, a core heatup occurred at a low core water level, although under a significant amount of PZR inventory, whose drainage seemed to be hindered owing to the pressurizer function by the RV. The transient of SBO-01 is well reproduced in the calculation using the MARS code.

• Journal of the Korean Institute of Gas
• /
• v.25 no.6
• /
• pp.74-79
• /
• 2021

This study analyzed the current status of the global hydrogen economy and the safety of energy sources currently in use due to the activation of the hydrogen economy. Understanding the hydrogen economy, identifying government policy trends, comparing and analyzing characteristics with existing energy sources such as gasoline, propane, and methane, and evaluating damage impact for each energy source using PHAST, a quantitative damage impact assessment program. Using the analysis results, this study analyzes the safety of hydrogen energy to revitalize the hydrogen economy and suggests ways to improve safety.

• Journal of the Korea Safety Management & Science
• /
• v.17 no.3
• /
• pp.89-96
• /
• 2015

The study was conducted with statical analysis of data (828 data in 2010, 752 data in 2012, 648 data in 2014) in order to evaluate laboratory awareness difference of research employees working in different types of universities. Results of the study were as follows: First, university institutes in the order of polytechnic colleges, university, and junior college showed the highest laboratory safety awareness in 'awareness and education of laboratorial safety regulation' and 'awareness in laboratory risk factors'. Second, the difference in safety awareness of universities by year(years that conducted current status survey) was the highest in year 2014, then in 2010, and in 2008. Third, the difference of research employees working for laboratory safety management by year(years that conducted current status) showed that university had the highest laboratory safety awareness in year 2010, but it changed to polytechnic colleges in year 2012 and 2014. Through this study, we could recognize the difference in safety awareness of research employees working in university institutes.

• Proceedings of the Korea Society for Energy Engineering kosee Conference
• /
• 2008.04a
• /
• pp.187-192
• /
• 2008

• Transactions of the Korean hydrogen and new energy society
• /
• v.29 no.5
• /
• pp.466-472
• /
• 2018

The investigation of cryogenic liquid pool spreading is an essential procedure to assess the hazard of cryogenic liquid usage. In this experimental study, to measure the evaporation velocity when the pool is spreading, liquid nitrogen was continuously released onto unconfined concrete ground. Almost all of the reported results are based on a non-spreading pool in which cryogenic liquid is instantaneously poured onto bounded ground for a very short period of time. A simultaneous measurement of the pool location using thermocouples and of the pool mass using a digital balance was carried out to measure the evaporation velocity and the pool radius. A greater release flow rate was found to result in a greater average evaporation velocity, and the evaporation velocity decreased with the spreading time and the pool radius.

• Nuclear Engineering and Technology
• /
• v.52 no.11
• /
• pp.2452-2459
• /
• 2020

Neutron spectrum is essential to the safe operation of reactors. Traditional online neutron spectrum measurement methods still have room to improve accuracy for the application cases of wide energy range. From the application of artificial neural network (ANN) algorithm in spectrum unfolding, its accuracy is difficult to be improved for lacking of enough effective training data. In this paper, an adaptive deviation-resistant neutron spectrum unfolding method based on transfer learning was developed. The model of ANN was trained with thousands of neutron spectra generated with Monte Carlo transport calculation to construct a coarse-grained unfolded spectrum. In order to improve the accuracy of the unfolded spectrum, results of the previous ANN model combined with some specific eigenvalues of the current system were put into the dataset for training the deeper ANN model, and fine-grained unfolded spectrum could be achieved through the deeper ANN model. The method could realize accurate spectrum unfolding while maintaining universality, combined with detectors covering wide energy range, it could improve the accuracy of spectrum measurement methods for wide energy range. This method was verified with a fast neutron reactor BN-600. The mean square error (MSE), average relative deviation (ARD) and spectrum quality (Qs) were selected to evaluate the final results and they all demonstrated that the developed method was much more precise than traditional spectrum unfolding methods.

• Nuclear Engineering and Technology
• /
• v.45 no.7
• /
• pp.871-894
• /
• 2013

KAERI (Korea Atomic Energy Research Institute) has been operating an integral effect test facility, the Advanced Thermal-Hydraulic Test Loop for Accident Simulation (ATLAS), for transient and accident simulations of advanced pressurized water reactors (PWRs). Using ATLAS, a high-quality integral effect test database has been established for major design basis accidents of the APR1400 plant. A Domestic Standard Problem (DSP) exercise using the ATLAS database was promoted to transfer the database to domestic nuclear industries and contribute to improving a safety analysis methodology for PWRs. This $2^{nd}$ ATLAS DSP (DSP-02) exercise aims at an effective utilization of an integral effect database obtained from ATLAS, the establishment of a cooperation framework among the domestic nuclear industry, a better understanding of the thermal hydraulic phenomena, and an investigation into the possible limitation of the existing best-estimate safety analysis codes. A small break loss of coolant accident with a 6-inch break at the cold leg was determined as a target scenario by considering its technical importance and by incorporating interests from participants. This DSP exercise was performed in an open calculation environment where the integral effect test data was open to participants prior to the code calculations. This paper includes major information of the DSP-02 exercise as well as comparison results between the calculations and the experimental data.

• Proceedings of the Korean Nuclear Society Conference
• /
• 2004.10a
• /
• pp.313-314
• /
• 2004

• Proceedings of the Korean Nuclear Society Conference
• /
• 2001.10a
• /
• pp.390-390
• /
• 2001