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Information × Registration Number 0209U006327, 0106U001571 , R & D reports Title Development of the methods for decrease radiation effect from radioactive waste management at NPP popup.stage_title Head Rudychev Volodimir Grigorovich, Registration Date 04-02-2009 Organization Kharkov national university named after V.N. Karazin popup.description2 Development of methods of diminishing of the radiation impact of radio-active waste of NPP was the purpose of implementation of three-year project on a personnel and environment, and also application of these methods for the evaluation of action of doses factors during transporting, storage and implementation of operations during processing the RAW in Ukrainian NPP. The object under investigation is the fields of radiations from the separate systems and technological complexes of NPP which work or is inculcated on the objects of atomic energy. The computer and experimental simulation of processes of transport of radiations is a research method in the matter and analysis of shield properties of existent buildings and facilities. As a result of the work in the first stage of project was investigational possibilities of acceleration of calculations of the fields of radiations outside of thick layer of bioshield of container storages of spent nuclear fuel and methods of description of the neutrons fields, that they are formed by an spent fuel at dry storage. Adaptation of the known programs of calculation of transport of radiations is executed for the decision of concrete modern tasks of NPP, which provided the reduction of time due to some special receptions and simplification of geometry of task. For verification of results of calculations the experimental information was used, got both directly on NPP and in special test-bench experiments on the bremsstrahlung sources. On the second stage of work executed development of the checking of brake radiation system which can be used for experimental research of transport of gamma-ray through heterogeneities in protective buildings. For measuring of brake radiation the analysed existent detectors and expected reviews of different scintillators were the method of computer design of processes of transmission of energy of radiations to the matter of detector and technical decisions of existent devices at the action on them of radiations which arise up athandling SNF on NPP. Selected the most effective materials and constructions which are let in on the ground in the systems of detection of brake radiation. The method of design of the fields of neutrons is created from containers which contain an exhaust fuel. Finishing stage of work made the analysis and determination of geometrical descriptions of containers with SNF, which at the set volume of cylinder container minimize the external radiation. For this purpose the calculations of power of dose of external gamma-radiation were executed for the standard and model form of barrels. Calculations the integrations of radiation of points sources conducted in approach on a volume and compared to Monte Carlo by a simulation. The optimum form of cylinder barrel is found for storage of RAW, what more economic after the charges of material and reduces power of dose in lateral direction on 10-15%. A question was also considered about optimization of chart of placing of containers from SNF or RAW different activity what would provide minimum doses round outside court of storage. As a result of implementation of this development the offered method of placing of containers taking into account different initial activity and its slump in course of time. It is experimentally investigational angular divisions of power of dose of gamma-radiation after passing of homogeneous or heterogeneous radiation shield by a thickness 5-6 free runs of gamma-rays. Obtained information will allow to specify radiation terms out of shield round technogenic sources, where usually there is a personnel. Product Description popup.authors popup.nrat_date 2020-04-02 Close