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Carbon filters--adsorbers are used in the third and fourth power-generating units of the second phase of the Leningrad nuclear power plant for catching gaseous and aerosol forms of radioactive iodine. They are installed in VTs-4 and -8 ventilation systems, where air enters from the space below the equipment and enclosures of the bottom water pipes, blowoff from the stub of the unloading-loading machine and the tank for emptying it, as well as cases with nonhermetic fuel assemblies. The airflow into ventilation systems equals 2300-8300 m3/h or, on the average, 6000 m3/h [I]. Iodine filters are installed three to four filters in parallel. The temperature of the filtered air equals 60-70~ and the relative humidity equals 90% (at 20 ~ The AUI-1500 carbon iodine absorber has the following characteristics: capacity (with velocity in the free cross section 0.4 m/sec) 1500 m3/h, height of the adsorption layer 40 cm, carbon mass 200 kg, absorber resistance 2.35-2.55 kPa, working temperature <60~ and dimensions 131.5 x 115 x 81.25 cm. Impregnated SKT-3I activated carbon is used as the adsorbent. The rated efficiency of radioiodine removal equals 98-99% [2]. However, this carbon is not produced commercially. For this reason, prior to August 1996 in the case of the fourth power-generating unit and up to now in the case of the third power-generating unit, AUI-1500 filters were filled with nonimpregnated SKT-3 carbon with the following characteristics [3]: bulk density 0.472 g/cm 3, apparent density (no voids) 0.75 g/cm 3, specific surface area 1100 m2/g, and fractional composition 3.6-1 mm (97%).In designs, the iodine carbon absorbers must meet several requirements. The adsorber must work in the entire temperature and humidity interval characteristic for normal operation and operation during an accident. Ordinarily, the maximum relative humidity is taken to be 98 %. The most important criterion is the duration of the contact (ratio of carbon volume to volume velocity of the flow or the height of the fill to the linear velocity), which should equal 1 sec and longer but not shorter than 0.5 sec. The purification efficiency increases with contact duration [4].The possibility of carbon dust being carried out of the filter imposes an upper limit on the velocity of the gas: the average gas velocity should not exceed 0.6 m/sec. The mass of the carbon fill must be calculated for absorption of iodine in all of its chemical forms. Furthermore, the geometry and dynamic resistance of the fill (the layer must be at least 30-cm high), the exposure dose from radionuclides accumulated in the filter, the ease of replacing carbon in the filter, and the possibility of leakage must all be taken into account.The efficiency of radioiodine absorption in carbon filters in VTs-4 and -8 ventilation systems was determined at the Leningrad nuclear power plant in 1993-1995 (Table 1). The 131,133I concentration in air was measured by the standard method by a team from the OOT and TB Office. The 131'133I removal factor calculated from the ratio K = Cin/Cou...
Carbon filters--adsorbers are used in the third and fourth power-generating units of the second phase of the Leningrad nuclear power plant for catching gaseous and aerosol forms of radioactive iodine. They are installed in VTs-4 and -8 ventilation systems, where air enters from the space below the equipment and enclosures of the bottom water pipes, blowoff from the stub of the unloading-loading machine and the tank for emptying it, as well as cases with nonhermetic fuel assemblies. The airflow into ventilation systems equals 2300-8300 m3/h or, on the average, 6000 m3/h [I]. Iodine filters are installed three to four filters in parallel. The temperature of the filtered air equals 60-70~ and the relative humidity equals 90% (at 20 ~ The AUI-1500 carbon iodine absorber has the following characteristics: capacity (with velocity in the free cross section 0.4 m/sec) 1500 m3/h, height of the adsorption layer 40 cm, carbon mass 200 kg, absorber resistance 2.35-2.55 kPa, working temperature <60~ and dimensions 131.5 x 115 x 81.25 cm. Impregnated SKT-3I activated carbon is used as the adsorbent. The rated efficiency of radioiodine removal equals 98-99% [2]. However, this carbon is not produced commercially. For this reason, prior to August 1996 in the case of the fourth power-generating unit and up to now in the case of the third power-generating unit, AUI-1500 filters were filled with nonimpregnated SKT-3 carbon with the following characteristics [3]: bulk density 0.472 g/cm 3, apparent density (no voids) 0.75 g/cm 3, specific surface area 1100 m2/g, and fractional composition 3.6-1 mm (97%).In designs, the iodine carbon absorbers must meet several requirements. The adsorber must work in the entire temperature and humidity interval characteristic for normal operation and operation during an accident. Ordinarily, the maximum relative humidity is taken to be 98 %. The most important criterion is the duration of the contact (ratio of carbon volume to volume velocity of the flow or the height of the fill to the linear velocity), which should equal 1 sec and longer but not shorter than 0.5 sec. The purification efficiency increases with contact duration [4].The possibility of carbon dust being carried out of the filter imposes an upper limit on the velocity of the gas: the average gas velocity should not exceed 0.6 m/sec. The mass of the carbon fill must be calculated for absorption of iodine in all of its chemical forms. Furthermore, the geometry and dynamic resistance of the fill (the layer must be at least 30-cm high), the exposure dose from radionuclides accumulated in the filter, the ease of replacing carbon in the filter, and the possibility of leakage must all be taken into account.The efficiency of radioiodine absorption in carbon filters in VTs-4 and -8 ventilation systems was determined at the Leningrad nuclear power plant in 1993-1995 (Table 1). The 131,133I concentration in air was measured by the standard method by a team from the OOT and TB Office. The 131'133I removal factor calculated from the ratio K = Cin/Cou...
The flow of iodine, including 131 I, into the coolant water in a nuclear power plant with an RBMK-1000 reactor under normal operating conditions and during transient regimes is analyzed. It is shown that under normal operating conditions the specific activity of 131 I in the coolant is correlated with the iron concentration. During shutdown, its content increases by factors of 30-200. The emission of 131 I into the coolant can be decreased by factors of 10-15 and the degree of unsealing of fuel elements can be decreased if before shutdown the reactor is held for 2-5 days at 50% of the nominal power level. Recommendations are made for decreasing 131 I emissions into the atmosphere. The adoption of these recommendations at the Leningrad nuclear power plant has reduced the 131 I emissions into the atomsphere by a factor of 17.The iodine concentration in the water coolant is correlated with the change in the reactor power and increases sharply at the moment a reactor is shut down. The specific activity of 131 I in RBMK-1000 coolant is observed to increase by factors of 30-200 during the first few days after shutdown (Fig. 1, Table 1).The yield of the ith fission product from unsealed fuel assemblies is described by the relationwhere K is the coefficient of proportionality, which depends on the reactor power; Y i is the total yield on fissioning, arb. units; λ i is the decay constant of the radionuclide, sec -1 ; b is an exponent which assumes values from 0 to 1, depending on the degree of defectiveness of the fuel elements: • b = 1 for an equilibrium mechanism of emission of fission products (the constant characterizing the emission of a radionuclide into the coolant is somewhat less than the decay constant of the radionuclide; a constant or equilibrium content of fission products is established in the fuel); point defect; no correlations between emission and power; • b = 0.5 with a diffusion mechanism of emission (the emission constant into the coolant is much greater than the decay constant); slit-shaped defects; exponential power dependence of the emission of the radionuclides; • b = 0 in the absence of emission; no defects; the radionuclides enter the coolant as a result of surface contamination of the fuel elements by uranium; the emission of fission products is proportional to the reactor power [1]. Once stationary equilibrium is reached, the rate of entry of fission products into the loop becomes equal to the sum of their rates of decay and removal from the loop. The equilibrium specific activity of the ith radionuclide in the coolant can be expressed by the formula (2) A KY M i i i i = + λ λ λ 0 5 0 . ,
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