Tests of how effectively CH 3 131 I and radioactive iodine are removed from air for the ventillation system of the VVRts reactor are performed. Carbon-fiber materials such as Busofite and fiber materials filled with impregnated OU-A carbon are studied as sorbtion-filtering materials. It is shown that these materials absorb iodine with approximately the same efficiency. The front layer traps I 2 . CH 3 I becomes distributed on several layers of the sorbing assembly. Iodine desorption from Busofite and the fiber material with OU-A is negligible (≤2%) over 114-3000 h. Recommendations are given for the composition of the fiber materials for removing iodine from air.The main components of gas-aerosol emissions from a nuclear power plant are radioactive inert gases, aerosols of radioactive fission products and activated products of corrosion, and volatile compounds of radioactive iodine. The most dangerous radionuclides from the radiation standpoint are 131 I and its volatile compounds [1,2].Filters of the type A-17 and D-23 (FPP and FPA-15 filtering materials) and AUI-1500 iodine adsorbers, equipped with SKT-3I granular activated charcoal, are ordinarily used to remove radioactive aerosols and gaseous forms of iodine from the gas-aerosol media of a nuclear power plant. SKT-3 carbon is impregnated with KI and various amines (TEDA -triethylenediamine, hexamethylenetetramine, and other substances) and/or AgNO 3 . Thermoxide (TiO 2 ), siloxide (SiO 2 ), and zeolites impregnated with AgNO 3 are used to remove iodine from gaseous media at temperatures above 100°C [3][4][5][6][7][8][9]. However, the fiber filtering materials used thus far have drawbacks. In practice, Petryanov filtering fabric based on perchlorovinyl polymer fibers in moist media becomes wet and loses its filtering properties. FPP material does not meet the fire safety and toxicity requirements [10], since it is combustible, and toxic substances are formed when it burns.Analysis of the efficiency of filters and carbon adsorbers, operating in the special ventilation systems of a nuclear power plant, has shown that the systems for removing aerosols and volatile compounds of iodine from steam-air media need to the improved because the removal efficiency is low and does not meet modern requirements [10,11]. The removal efficiency is 93-96% for radioactive aerosols and 28-94% for volatile forms of iodine but in most cases it is 67-83%. The low iodine removal efficiency is due to, among other things, inadequate sorption efficiency for organic forms of iodine sorbed by SKT-3 activated carbon and the possibility that these forms of iodine are not sorbed.

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 present article is devoted to investigating the laws governing the behavior of radioactive iodine in RBMK-1000 (high-power channel reactor) systems and its discharge by a special ventilation system, using the example of the third and fourth power units of the Leningrad nuclear power station (second phase).The gas and aerosol discharge is formed in several stages (see Fig. 1). The main reason for the appearance_of radioiodine in the discharges from a nuclear power station is failure of the fuel-element seals leading to an increase in its specific activity in the coolant of the multiple forced-circulation loop. Direct emergence of the radionuclide into the environment is prevented by a multibarrier radiation shield system: the fuel matrix, the fuel-element jacket, the coolant loop, and the sealed cells, nuclear power station areas, and effluent cleaning systems.

The efficiency of radioactive iodine recovery was studied as influenced by the type of filtration material and sorbent (OU-A carbon), sorbent surface density, and type and concentration of impregnating agent (AgNO 3 , TEA, KI, BaI 2 , etc.). A regression equation adequately describing the correlation dependence of 131 I break through the sorption3filtration material on the sorbent surface density (OU-A carbon, 50 3 200 g m !2 ) and impregnating agent concentration (AgNO 3 and TEA, 1325 wt %) was obtained. The dynamic capacity of impregnated OU-A carbon for molecular iodine was determined; it varies from 170 to 350 mg g !1 .Based on these experimental results, a heat-resistant sorption3filtration material (Filosorb-D) for recovery of radioactive iodine was developed; this material consists of one or two layers of filtration material (FPA, PP3 PE) containing imbedded impregnated OU-A carbon (100 3500 g m !2 ) and one layer of FSB-75-11 or MVFE-22 filtration material to remove aerosols. The operation properties of the Filosorb-D sorption3filtration material are as follows: filtration velocity up to 6 cm s !1 , aerodynamic resistance <480 Pa, efficiency of radioactive iodine recovery 99.0 399.9%, operation life 10 000 315 000 h, and desorption of radioactive iodine and sorbent carry-away <132%.Radioactive 131 I is one of the most environmentally hazardous radionuclides owing to its high uptake by human body, especially by the thyroid gland. Due to the variety of chemical species, efficient removal of radioactive iodine from gaseous aerosols is a complex problem.Combined filter3sorbents based on fibrous sorption materials show promise in this respect. To develop such filters, it is necessary to select filtration materials (FMs) and sorbents with the high efficiency of recovery of various iodine species and with the required physicochemical properties, to develop optimal compositions of sorption and filtration materials, and to determine their performance, capacity, and operation life.The required materials were chosen and developed using the data obtained by Borisov et al. in studying sorption3filtration materials for recovery and analysis of iodine radionuclides, performed at the Karpov Research Physicochemical Institute [135].However, owing to their insufficient moisture and heat resistance and mechanical strength, these materials are unsuitable for charging filter3adsorbers of ventilation systems. More resistant and stronger materials with a structure allowing high filling with fine activated carbon and other sorbents should be developed. It is necessary to select available and effective impregnating agents and to determine their optimal concentration in the sorbent. In so doing, the volatility, heat resistance, and toxicity of the impregnating agents and the efficiency of iodine recovery by the impregnated sorbent as influenced by the water content should be taken into account.Thus, development of appropriate sorption3filtra-tion material (SFM) for iodine filter3sorbent involves selection of appropriate filtration...