[en] The quantity of liquid waste produced during HANARO operation for the years from 1996 to 2002 has been investigated and the interrelation with the reactor power output has been analysed. The waste amount produced during this period was 263,530 l and the processing expense was 81,690,000 won. The waste amount and processing expense per reactor power output are 11.38l/MWD and 157 won/MWD, respectively. The waste has been reduced by improving repair work procedure and experiment process in the reactor hall

[en] The quantity of the gaseous radioactive waste generated from HANARO operation for the years from 1996 to 2002 has been investigated. The amounts of Ar-41, H-3 and I-131 exhausted to the environment were 6.33E13 Bq, 5.10E12Bq and 3.26E8 Bq, respectively

[en] The quantity of solid waste produced during HANARO operation for the years from 1996 to 2002 has been investigated and the interrelation with the reactor power output has been analysed. The waste amount produced during this period was 69,599 l and the processing expense was 1,878,000 won. The waste amount and processing expense per reactor power output are 3.01 l/MWD and 811 won/MWD, respectively. A dry equipment for the spent resin was developed and the spent resin volume has been reduced by about 40% by using it

[en] During the normal operation of HANARO. The radionuclide in the primary coolant are analysed, and the possibility for fuel failure detection by the analyses is investigated. The analysis of radionuclides performed by using the HPGe gamma-ray detection system, and most nuclide which represent the peaks are confirmed by using the gamma-ray spectrums measured for 30 minutes, 2 and 17 hours. Also, the analyses for the radionuclide of coolant for 6 months are compared with the measurements of delayed neutron in the primary cooling circuit and the result of analyses is similar to the variation of the measurements of the delayed neutron. So the nuclide and gamma-ray peaks which can detect the fuel failure are determined, and the nuclide are Xe-138(434 keV), I-134(846 keV) and Cs-138(1435 keV). Therefore, the possibility for fuel failure detection by using the analysis of radionuclide in primary coolant is verified

[en] The quantity of radioactive waste generated from HANARO operation for the years from 1996 to 2002 has been investigated. It was found that the solid waste of 69,598 liter and liquid waste of 263,530 liter have been generated for the past 7 years. The amounts of Ar-41, I-131 and H-3 exhausted to the environment were 1,161.9 Ci, 8 .8x 10^-3 Ci and 137.7 Ci, respectively. A spent resin dry equipment was developed and its use brought the reduction of spent resin volume by about 40%. The sealing of leak points in Pneumatic Transfer System and the continuous feed of nitrogen gas to the system contribute to the reduction of Ar-41 concentration in the exhaust air

[en] The yearly operation time and the number of users in HANARO are increasing since its initial criticality has been achieved in 1995. This achievement is partly in debt to the spread of safety culture to operators and reactor users. In this paper, the activities done by the reactor operation organization on safety culture are described, and their further efforts identified to be necessary for the improvement and dissemination of safety culture and are presented

[en] The primary coolant purification system of HANARO is required to maintain the chemical state of the reactor coolant and pool water within the specified limits. For this, reactor operators replace periodically the resin of ion exchanger and this is one of the operator activities which could bring large radiation dose. Therefore, we analysed the radiation level at the surface of resin cartridge from the previous replacement activities and found the required resin decay time to meet the limit specified for radiation protection. As results, three more resin cartridge were found to be required for the primary purification system to meet the radiation protection limit. This was effective in reducing the radiation dose to operators

[en] For the standardization of the time to execute HANARO start-up and shutdown procedures, code names were assigned to the individual procedures and the work time were investigated. The data recorded by the operators during start-up and shutdown were statistically analyzed. The analysis results will be used for the standardization of start-up and shutdown procedures and it will be reflected in the procedure document

[en] Water-quality control of the second cooling system in HANARO has been altered from low Ca-hardness treatment to high Ca-hardness treatment since March, 2001. High Ca-hardness water treatment in HANARO is to maintain the calcium hardness around 12 by minimizing the blowdown of secondary cooling water. This paper describes the effect of cost reduction after change of water-quility treatment method. The result shows that the cost of the water could be reduced by 25% using the pond water in KAERI. The amount and cost for the chemical agent could be reduced by 40% and 10% respectively

[en] By using the amount of power generation, the delay hours in full-power arrival and those in shutdown as parameters, the operation record of HANARO in the year 2002 was analysed and the results were compared with those for the year 2001. The amount of power generation in 2002 was 4852 MWD, which is larger than that of 2001 by 1082 MWD and is the highest in record after initial criticality. The delay hours in full-power arrival and the delay hours in shutdown was 3.56 and 2.49 hours for 2001, respectively. Those for 2002 were 0.29 and -0.38 hours. This quantitative and qualitative improvement is believed to be in debt to the following measures; 3 week plan for activities including maintenance and experiment, the reduction of fuel inspection amount and starting-up the reactor by one hour early