For the thermophysical calculation of a fuel element, it is necessary to know the radial distribution of energy release in the fuel core, which influences the temperature field in the field core [1], and the consequent radial distribution of burnup in the fuel core. It is especially important to know the radial distribution of fuel burnup for average (over the transverse crosssectional area of the fuel element) burnup exceeding 45-50 MW.day/kg, when it starts to exceed 60-75 MW.day/kg in a thin peripheral layer. This level of burnup is the threshold from the standpoint of the formation of an easily distinguishable, altered, microstructural region at the boundary of the fuel tablet --the so-called rim layer [2]. This layer is characterized by the presence of many small gas bubbles, vanishing of the initial grainy structure, and formation of new, much smaller, grains (less than 1 ~tm).The surface layer strongly influences the integral characteristics of the fuel element as a whole. The fuel in this layer is characterized by a sharp decrease of the thermal conductivity and strength and a substantial intensification of the yield of gaseous fission products, including the athermal yield. The formation and development of such a layer results in the production of a thermal barrier in the path of the heat from the fuel and degradation of thermal conductivity of the fuel--casing gap accompanying the escape of gaseous fission products. As a result, the fuel temperature increases substantially, the total yield of gaseous fission products increases, and in consequence the pressure of the gas medium under the casing increases significantly; in the case of burnup along the fuel element exceeded 60 MW.day/kg, the pressure could become a determining factor influences the working capacity of the fuel element.In the present work, we calculated the radial distribution of energy release and burnup in the fuel core as a function of the burnup averaged over the transverse cross section. In the calculations, the transverse cross section of the fuel core v, as divided into 20 zones of equal area and, depending on the burnup, the change in the nuclide composition of the fuel and the relative energy release were determined in each zone.In the fuel elements of power reactors (with low-enriched fuel), the change in energy release at the initial moment of operation is small and is caused by the decrease in the thermal-neutron flux density as a result of absorption of the neutrons primarily in the outer layers of the fuel. With burnup, however, plutonium, which is formed as a result of resonance absorption of the moderated neutrons by 238U nuclei, accumulates. This accumulation is most rapid in the outer layer of the fuel. The redistribution of the fissioned isotopes along the radius of the fuel core increases the nonuniformity of energy release [1].The neutron-physical characteristics of two types homogeneous BBER-440 assemblies were calculated, using the fuel assembly program [3] in application to a core with 349 fuel assemblies with initi...

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A method of performing stationary thermomechanical calculations of VVÉR-440 and -1000 fuel elements, using the TRANSURANUS computer code to obtain the dependence of the temperature and radius of the fuel elements on the lineal power ensity and burnup, is described. These dependences are intended for use in neutron-physical calculations of the VVÉR reactor at the Kozlodui nuclear power plant in stationary and transient regimes. The results obtained with this computer program are compared with calculations performed using the certified TOPRA-s code. The comparison shows reasonable agreement between the results of calculations of the fuel temperature.Three-dimensional calculations of the core in stationary and transient regimes, performed using neutron-physical, thermohydraulic, and thermomechanical programs, based on a realistic representation and description of the state of the fuel for any moment of operation, are necessary for analyzing the physics and safety of VVÉR reactors. The real state of the fuel is determined by the instantaneous thermophysical and deformational characteristics of the fuel elements, varying as a result of complex intercoupled radiative, thermal, mechanical, and other processes. Models, computational approximations, and correlations are becoming increasingly more accurate because of the need to describe the fuel characteristics more accurately during operation in a reactor.The present paper describes a method for performing stationary thermomechanical calculations of VVÉR-440 and -1000 fuel elements using the TRANSURANUS program [1] to obtain the dependence of the temperature and radius of fuel elements on the liineal power density and fuel burnup. These dependences are used in neutron-physical calculations of VVÉR reactors at the Kozlodui nuclear power plant in stationary and transient regimes. The results obtained with this computer program are compared with calculations performed with the TOPRA-s computer program [2, 3] (certificate No. 126, April 12, 2001, from the Scientific-Technical Center of the Nuclear and Radiation Safety of the State Atomic Inspection Agency of the Russian Federation). The data from the comparison show reasonable agreement between the calculations of the fuel temperature.Determination of the Computational Characteristics of VVÉR Fuel Elements. Many parameters determine the dependences of the temperature and radius of a fuel kernel on the power and burnup: the irradiation history (time dependence

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