Fixed Radiation Source Tracking System

• Design and manufacture of location tracking monitor
• Development of central control system based on GIS
• Location change monitoring data transmission and reception and central control system DB interoperability test, reliability analysis

• A surveillance equipment for tracking the status of the fixed radiation source and related system facilities.
• A central control system for providing information on the monitoring status to the manager.

• This system monitors the in-operation period of the fixed sources.
• RSTS (Radiation Source Tracking System) provides information on radiation source usage to the regulatory body.
• The core technology of RSTS is to detect the power source usage of the radiation source, to monitor whether the power cord is disconnected, to transmit and receive data, and to operate the central control system based on the geographic information system.

The nuclear fuel cladding tube is made through pilgering and annealing process. Pickling process is needed to remove oxide film and foreign material on the tube surface. The Zirconium(Zr) becomes dissolved in acid solution during the pickling process. Normally the pickling waste solution with the dissolved Zr is discarded as waste.

It is desirable to establish an eco-friendly full recycling plant system where the zirconium in the waste solution is fully retrieved and the waste solution is treated and re-used.

• The spent waste pickled solution generated during the process of cleaning the Zr(Zirconium) alloy cladding tube of nuclear fuel rod is re-cycled to reduce
• waste generation by more than 90%.
• Pure Zirconium and Zirconium alloys (CuZr) are deposited and re-cycled through electrowinning from the salt compound obtained by the precipitation reaction.

NSE Technology is developing a spent nuclear fuel(SNF) storage cask monitoring system. Since the SNF storage cask should be operated under passive natural cooling conditions without external power for over 20 years, monitoring activities are needed for thermal performance, confinement and radiation shielding requirements. This monitoring system is to detect the anomalies in confinement condition of the cask and excessive increase of fuel cladding temperature for a long period.

• Temperature sensors: Temperature sensors are attached on the surface of the casks.
• Transmitting communication modules: These modules are installed in each cask and they collect and wirelessly transmit signals from the temperature sensors.
• Receiving communication modules: These modules are installed at each cask placement area. These modules receive temperature signals from the transmitting communication modules and send the temperature data to the server through internet.
• Temperature and pressure algorithm sets: These algorithm sets are formulated using results from the thermo-fluid dynamic analysis on the casks and then loaded on the server.
• Integrated monitoring platform server: This server contains the database of temperature and pressure algorithm sets and decision logics for anomalies, and it provides on-screen representation of information on the cask status.

• The main design goal of Cask Monitoring System is to ensure that the operating parameters of the onsite dry spent fuel nuclear fuel storage casks are maintained within the range specified in the design certificate.
• This monitoring system is designed to detect anomalies in confinement condition of the cask and excessive increase in fuel cladding temperature over a long period of time (20 years).

The power supply used for safety and non-safety instrument and control system of nuclear power plant is recognized for its high reliability, and high quality technology.
Two switching mode power supplies (SMPS) are installed in a single bay for redundancy. Use of SMPS makes it lighter in weight and easier to maintain compared to linear type power supplies.

NSE Technology provides professional evaluation on the results of safety analyses performed for nuclear power plant design and licensing. Safety analysis covers LOCA analysis for evaluating the adequacy of Emergency Core Cooling System design and non-LOCA analyses. Thermal-hydraulic system codes such as MARS or RELAP5 are used, and reactor kinetics and fuel analysis codes can additionally be coupled to the system codes for detailed core evaluation during the transients.

• Technical support in detailed evaluation of containment spray actuation event of ShinKori Unit 1.
• RETAS workbench functional upgrade and validation on integral effect tests
• Pre-analysis on simulator for regulatory audit and training and development of a prototype engine
• Core nodalization effects in the main steam line break analysis using the MARS/PARCS Coupled Code
• Development of an Integrated Safety Analysis System Coupling Irradiated Fuel Performance Model.

• Fuel performance analysis considering fuel burnup needs to be integrated in the plant system analysis.
• Methodology has been developed for using the MARS-FRAPTRAN coupled code system