[en] Steady state fuel test loop will be equipped in HANARO to obtain the development and betterment of advanced fuel and materials through the irradiation tests. The HANARO fuel test loop was designed to match the CANDU and PWR fuel operating conditions. The accident analysis was performed by RELAP5/MOD3 code based on FTL system designs and determined the detail engineering specification of in-pile test section and out-pile systems. The accident analysis results of FTL system could be used for the fuel and materials designer to plan the irradiation testing programs. (author). 23 refs., 20 tabs., 178 figs

[en] Manufacturing process of IPS Mock-up was initiated in late of 2003 with DAEWOO Precision industries Company. Manufacturing drawings due to detail drawings are composed of Outer assembly and Inner assembly. Welding of IPS Mock-up was performed by the GMAW(Gas Metal Arc Welding) process. After the welding process, non-destructive examination was conducted. Leak test was performed to the Main cooling water part and Neon gas inter-space gap part by the He gas injection with the pressure of 6.0 kg_f/cm² and 30 minutes holding time. the result was shown that there was no leak at the Neon gas inter-space gap part but leak was occurred at Main cooling water part according to imperfect screw of purge plug. so, it was re-finished and test was performed to certify the leak tightness. To satisfy the HANARO Limiting Operation Condition, IPS should be tested ahead of installation at the HANARO reactor by the use of test facilities. IPS Mock-up and its test facilities will be designed and used for the test of 'HANARO flow tube pressure drop', 'IPS inner pressure drop' and 'IPS inner vibration'

[en] A fuel test loop has been developed in HANARO for nuclear fuel irradiation tests. The facility provides experimental conditions similar to the normal operational pressures, temperatures and water chemistry of commercial pressurized-water reactors. The project for the fuel test loop development began in December 2001. And then the design for the out-pile system, which is a processing system, ended in April 2004 and the design for the in-pile system ended in October 2004. The construction of the facility were done from July 2006 to March 2007. The cold function tests were performed since April 2007 and the hot function tests were completed by May 2009. The safety analysis report was prepared by the end of 2004. The change of HANARO operation license was requested to the ministry of science and technology on January 6, 2005 in order to install and operate the fuel test loop in HANARO. Thereafter on July 21, 2007 the ministry of science and technology approved the change of HANARO operation license with 10 pending items. The 10 pending items including safety analyses on the first test fuels should be resolved before the fuel test loop operation. Therefore the design and safety analyses of the test fuels were carried out and reviewed by Korea Institute of Nuclear Safety. Finally the 10 pending items were resolved completely by September 1, 2009

[en] The analyses of anticipated operational occurrences of the HANARO fuel test loop have been carried out by using the MARS/FTL_A code, which is a modified version of the MARS code. A critical heat flux correlation on the three rods with triangular array was implemented in the MARS/FTL_A code. The correlation was obtained from the critical heat fluxes measured at a test section, which is the same geometry of the in-pile test section of the HANARO fuel test loop. The anticipated operational occurrences of the HANARO fuel test loop are the inadvertent closure of the isolation valves, the over-power transient of the HANARO, the stuck open of the safety valves, and the loss of HANARO class IV power. A minimum DNBR (Departure from Nucleate Boiling Ratio) was predicted in the inadvertent closure of the isolation valves. It is indicated that the minimum DNBR of 1.85 is greater than the design limit DNBR of 1.39. The maximum coolant pressure calculated in the anticipated operational occurrences is also less than the 110 percents of the design pressure

[en] The paper describes the design development with high pressure Fuel Test Loop for both of PWR and CANDU type fuel testing under simulated power reactor conditions in the HANARO reactor. The Fuel Test Loop consists of in-pile test section (IPS) and out of pile system (OPS). The IPS is connected to the OPS by means of which the system pressure, the system temperature and the water quality are controlled and regulated. Power reactor requirements are generally applicable to the fuel Test Loop and have been applied judiciously. In many respects the Fuel Test Loop is analogous to a direct cycle power reactor. As such it is appropriate to place the normal heat sink outside the reactor coolant pressure boundary. The design of the Fuel Test Loop is completed except some parts of the FTL and the equipment of the OPS are under fabrication. Also the safety analysis report was submitted to the Korea Institute of Nuclear Safety (KINS) to get the license of installation and operation of the Fuel Test Loop. (author)

[en] An emergency shutdown procedure for the HANARO fuel test loop has been developed. The facility has two kinds of emergency shutdown functions if an emergency occurs in the fuel test loop. One is the HANARO's emergency shutdown and the other is the emergency shutdown of the fuel test loop. The emergency shutdown of the fuel test loop means isolating the in-pile test section from non-nuclear safety systems and cooling the in-pile test section by using the emergency cooling water system. The emergency shutdown procedure should be carried out with the reactor shutdown procedure (ROP-OP-29) because the cooling capability of the emergency cooling system has been designed assuming that the fission power of test fuels decreases abruptly due to the fast shutdown of the HANARO. The emergency shutdown procedure includes trip signals of the reactor and the fuel test loop, automatic actions of the fuel test loop control system, operator's actions, and system recovery procedures after the emergency shutdown. A flow chart to find out what kinds of accidents occur also included in the procedure

[en] A start-up and shutdown procedure for the HANARO fuel test loop has been developed. This is a facility for fuel and material irradiation tests. The facility provides experimental conditions similar to the normal operational pressures and temperatures of commercial PWR and CANDU plants. The normal operation modes of the HANARO fuel test loop are classified into loop shutdown, cold stand-by 1, cold stand-by 2, hot stand-by, and hot operation. The operation modes depend on the fission power of test fuels and the coolant temperature at the inlet of the in-pile test section. The HANARO must maintain a shutdown mode if the HANARO fuel test loop is loop shutdown, cold stand-by 1, cold stand-by 2, or hot stand-by. As the HANARO becomes power operation mode, the operation mode of the HANARO fuel test loop comes to hot operation from hot stand-by. The procedure for the HANARO fuel test loop consists of four main parts such as check of initial conditions, stat-up operation procedure, shutdown operation procedure, and check lists for operations. Several hot test operations ensure that the procedure is appropriate

[en] Documents produced during the design, procurement manufacturing, and commissioning stage for the instruments such as SPND, Thermocouple, and LVDT which are installed on the In-pile section(IPS) of the fuel test loop(FTL) are gathered together. The values measured by the instruments are stored on the database of the data acquisition system(DAS) and displayed through both DAS and remote monitoring system installed on the users office. The commissioning status and the problems and items to be improved which are revealed during the commissioning stage are described. The report will be used for the development and operation of the instruments in the near future

[en] A fuel test loop (FTL) for irradiation tests is under development at the HANARO. The construction of the fuel test loop was completed at the beginning of this year and pre-service tests are being carried out. The design basis accidents and operational occurrences (AOOs) have been completed for the fuel test loop including test fuels for pressurized water reactors. The fuel test loop has no any means to control the power of test fuels. The thermal power of the test fuels depends on the power of the HANARO. This paper deals with the thermal-hydraulic transient analysis and the prediction on a departure from a nucleate boiling ratio (DNBR) during an over-power transient of the HANARO, which is one of the AOOs

[en] The analyses of the postulated loss-of-coolant accidents of the HANARO fuel test loop have been carried out based on the evaluation method as described in the KINS/GT-N007-1. Double-ended guillotine breaks and longitudinal splits of pipes have been investigated. MARS/FTL code has been used for the analyses of the loss-of coolant accidents. Evaluation models such as the Moody model for discharge rate calculation and the Baker-Just model for water-metal reaction calculation were used. Multipliers were also introduced to the correlations of heat transfer coefficients in the MARS/FTL code in order to calculate conservative cladding temperatures for accidents. Consequently the maximum cladding temperatures are 1286K(1012.9 .deg. C) and 1264K(990.9 .deg. C) for PWR and CANDU fuel test modes respectively. The location of pipe break is the cold leg in the HANARO pool and the type of pipe break is the longitudinal split of pipe. The maximum cladding temperatures are less than the design limit of the fuel cladding temperature for PWRs