[en] The solvent extraction separation cum radiochemical analysis method is modified for the estimation of iodine species in aqueous medium. The species determined are elemental iodine, iodide and iodate ions, organic iodide and colloidal iodines present in sub-ppb levels of concentrations. Speciations of iodine in synthetic aqueous samples as a function of acidity as well as reactor water samples from Tarapur Atomic Power Station (TAPS) Boiling Water Reactors is studied using this modified method. (author)., 4 refs., 2 tab

[en] A method for the removal of suspended alumina particles from H₂O/D₂O systems has been developed. It is based on the modification of surface charge of the suspended hydrated alumina particles by the addition of sulfate ions and adsorbing them on conventional strong base anion exchanger. 48 ppM of added sulfate has been found to be the required concentration for treating 30 ppM Al₂O₃ x 3D₂O suspensions. 7 refs., 4 tabs

No abstract available

[en] Vanadous based LOMI formulation very effectively dissolves corrosion product oxides in nuclear reactor systems and thus has proved to be a very efficient decontamination agent. The preparation of Vanadous formate with Hg pool as cathode is already studied by us. However, large scale preparation of LOMI involving Hg pools poses many practical problems. Hence a variety of cathode materials such as simple stainless steel mesh, platinum mesh, mercury coated platinum mesh and lead foil have been studied as alternatives. This paper presents the results of these studies and assesses the suitability of these for large scale LOMI preparation. (author)

[en] Decontaminating a system or a sub-system for decommissioning involves reducing the radioactivity levels to background values so that these materials may be disposed off as scrap. In this respect the use of oxidative formulation containing Ce⁴⁺ and mineral acids like HNO₃ and H₂SO₄ for stainless steels is reported. However, the nature of the container material to carry out component decontamination for decommissioning using these strong formulations needs evaluation. This paper brings out the compatibility studies of Stainless Steel and HDPE carried out in these oxidative formulations and compares them with those carried out in organic acid based reductive formulation like CEA. The results of magnetite powder dissolution kinetics in both oxidative and reductive types of formulations are also given. The studies show that HDPE is a more compatible container material than others with the oxidative formulations while dissolution rate constant is 10-50 times higher in reductive than in oxidative formulations. (author)

[en] Conventional polystyrene-based strong acid cation and strong base anion exchangers have been evaluated for the retention of ⁶⁰Co from vanadium based low oxidation-state metal ion (LOMI) decontamination formulation. Cation exchange treatment results in decontamination factors (DFs) of 8--40 with respect to ⁶⁰Co if the LOMI solution is treated immediately after decontamination but yields lower DFs of 3--4 if it is stored for >24 h under ambient conditions. In both cases, anionic treatment of the cation column effluent gives DFs in the range 45--400. These results point to the differential speciation of ⁶⁰Co in fresh and stored LOMI solutions and hence the necessity of having both cation and anion exchange treatments for the near complete removal of ⁶⁰Co. Coprecipitation with MnO₂ obtained by mixing the used LOMI solution with the required amounts of alkaline KMnO₄ employed for pretreating the oxide surfaces was also found to be an effective method for ⁶⁰Co removal. From the point of view of total activity removal, the precipitation method was less efficient than ion-exchange method

[en] Radioactive liquid wastes generated during chemical decontamination of specimens of coolant system surface from Tarapur Atomic Power Station's boiling water reactors were processed by ion exchange. The cation exchanger effectively removed the Co-60 radioactivity from fresh low oxidation state metal ions (LOMI) (85%) but not from stored LOMI. A combined cation-anion exchange treatment produced a totally inactive and chemically pure effluent. (author). 3 refs., 1 fig

[en] The physico-chemical aspects of coolant water is an important part of the site evaluation before the construction of a power station. This paper deals with the survey of the coolant seawater at Tarapur Atomic Power Station (TAPS) intake and its practical implication for the proposed 500 MWe power plant at the adjacent site. (author). 6 refs., 1 tab

[en] The report is divided into three sections. The first section contains a general introduction to ion exchange resins used in various processes, the second section describes characteristic properties of the polymer materials and the inter relation between them. This will, in turn, be useful to interpret the data obtained from the various tests carried out on the resins in the laboratory. In the third section of the report, are given the details of each method used for a particular test to be carried out on a routine basis. Each method describes the principle involved, the reagents and apparatus used in the experiment, the actual procedure and calculations and recording of the data. 3 refs. (author)

[en] The behaviour of radioactive iodine species in aqueous boiling water reactor (BWR) coolant has been studied during constant power reactor operation, during power reduction and under shutdown conditions at Tarapur Atomic Power Station. It was observed that iodide and iodate species are the major contributors to the iodine spiking during power reduction. (author). 3 refs., 1 tab