Comparison of the cracking resistance characteristics of the base metal and the welded joints of reactor vessels

Skoda Industrial Combine, Czechoslovak Federal Republic. Central Scientific-Research Instituteof KM Prometei. Gidropress Experimental Design Office. NIKIÉT. Translated from Atomnaya Énergiya, Vol. 72, No. 3, pp. 246–251, March, 1992.     

Behavior of HTGR coated fuel particles and elements in tests under normal and accident conditions

Scientific-Industrial Organization Ray. Russian Scientific Center Kurchatov Institute. Siberian Division, Scientific-Research Construction Institute of Power Engineering. Translated from Atomnaya Énergiya, Vol. 73, No. 3, pp. 189–195, September, 1992.     

Prospects of using thermoelectric nuclear power generators for manufacturing of materials in space

State Enterprises Krasnaya Zvezda. Nuclear Reactor Institute of Kurchatov Institute Scientific Center. Translated from Atomnaya Énergiya, Vol. 75, No. 4, pp. 254-259, October, 1993.     

Change of the physical properties of zirconium carbide in a short exposure to a neutron current

Scientific Planning Department LUCH. Translated from Atomnaya Énergiya, Vol. 70, No. 1, pp. 55–56, January, 1991.     

Radionuclide contamination and dose rates in Russia and Belarus after Chernobyl accident

Institute of Experimental Meteorology, Scientific-Industrial Organization Typhoon. Translated from Atomnaya Énergiya, Vol. 73, No. 3, pp. 234–238, September, 1992.     

New generation of boiling-water-reactor nuclear power plants of increased safety

Scientific-Research Construction Institute of Power Engineering. Russian Scientific Center Kurchatov Institute. Special Design Office of Industrial Organization Izhorskii Plant. All-Union Scientific-Research and Design Institute of Power Engineering Scientific-Industrial Organization. Translated from Atomnaya Énergiya, Vol. 73, No. 1, pp. 13–19, July, 1992.     

Transforming a VVÉR-440 to a five-year fuel cycle

Kurchatovskii Institute, Russian Scientific Center. Gidropress Special Design Office. Kolskii Nuclear Power Plant. Translated from Atomnaya Énergiya, Vol. 73, No. 2, pp. 168-170, August, 1992.     

Deformation systems of α-zirconium

The deformation systems of -zirconium iodide have been studied in coarse-grained polycrystalline specimens deformed by upsetting. The orientation of the grains was determined from Laue patterns obtained in a special back-reflection camera using a small-diameter beam. The indices of the deformation systems were determined by the two-surface method and by the pole locus method.It was found that -zirconium is deformed by slip along the plane in the direction and along the plane. A number of twinning systems have been discovered In -zirconium: a) K₁ , 1 , K₁ , ₂ and s=0.173; b) K₁ , ₂ [1126], K₂ (0001), ₂ [1120] and s=0.629; c) K₁ (1122), ₁ [1123] and in one case, d) K₁ , ₁ .     

Radiation stability of ZnSe(Te) crystals

Scientific-Industrial Association Monokristallreaktiv. Translated from Atomnaya Énergiya, Vol. 70, No. 2, pp. 119–121, February, 1991.     

Determination of plutonium in soil and bottom sediments in the region of the scientific-research institute of atomic reactors

Scientific-Industrial Firm The Radium Institute. Scientific-Research Institute of Atomic Reactors, Dimitrovgrad. Translated from Atomnaya Énergiya, Vol. 75, No. 4, pp. 319-324, October, 1993.     

Problem of the iodine method of purification of zirconium

A method is proposed for the determination of the equilibrium constantsk and k' for the reactions Zr+2I₂–ZrI₄=0 and 2I–I₂=0, which is based on the measurement of the amount of iodine or zirconium liberated in the decomposition of zirconium tetraiodide on a heated surface in the process of establishing equilibrium. The decomposition of the tetraiodide was carried out at 900–1600C on a tungsten filament. The temperature distribution between filament and vessel walls was neglected.The dependence of the sum of atomic and molecular iodine pressures on zirconium tetraiodide pressure was determined at 1430C, and on temperature for 50 mm Hg. The values of kk'² 35 (mm Hg)³ at 1430C and k0.07 mm Hg at 400C, found from the results, differ substantially from known thermodynamic data, but give good agreement between the authors' formula [1] and experimental results on the iodide process of zirconium purification.     

Calculating the transient temperature field in a reactor tube and the thermoelastic stresses in the fuel element cladding

Approximate analytic methods are given for calculating the transient temperature field in the fuel elements and the coolant temperatures at any point along the reactor tube, as well as the transient thermoelastic stresses in the cladding of a cylindrical fuel element. The coolant temperature at the input to the tube is constant, and the coolant undergoes no changes in state of aggregation. The approximate methods are illustrated by examples.Results are given, for comparison, of accurate calculations of the same examples made with a rapid calculating machine.List of symbols time - r; z coordinates (radius, distance along tube) - r₁; r₂ internal and external radii of fuel element cladding respectively - H total active length of fuel element - a₁; ₁;c _{1 1} coefficients of temperature conductivity, heat conductivity, specific heat capacity and specific gravity of fissionable material respectively - a₂; ₂; C_p2; ₂ cladding parameters - a; ; c_p; coolant parameters - mean cladding radius - f:f₂ cross-sectional area of tube for coolant and cladding respectively - w coolant velocity - coefficient of heat release to coolant - t (r, ); (); () fuel temperature, mean temperature over cross section of cladding, and coolant temperature at pointz. along tube respectively - qv() specific volume of coolant at pointz - values averaged overz - quantities at the initial instant of time - ₃ delay time - _n time required for coolant to go from z=0 to the point in question     

Single-loop nuclear power plant with a pressurized-water reactor

Trust Tsentroénergomontazh. Translated from Atomnaya Énergiya, Vol. 71, No. 5, pp. 458–460, November, 1991.     

Determination of leaching factors and effective diffusion coefficients of radionuclides from the results of long tests

radon Scientific-Industrial Amalgamation, Moscow. Translated from Atomnaya Énergiya, Vol. 70, No. 3, pp. 196–197, March, 1991.     

Selection of the coolant for thermionic-emission nuclear power-generating plants in spacecraft

Scientific Production Association Krasnaya Zvezda. Translated from Atomnaya Énergiya, Vol. 72, No. 3, pp. 241–246, March, 1992.     

Thermal stability of scintillation detectors based on hygroscopic alkali-halide crystals

Scientific Planning Department Monokristallreaktiv. Translated from Atomnaya Énergiya, Vol. 70, No. 6, pp. 413–414, June, 1991.     

Oxygen transport in the system niobium-uranium dioxide

Luch Technological Society. Translated from Atomnaya Énergiya, Vol. 71, No. 1, pp. 62–64, July, 1991.     

Thermionic space nuclear power systems within the “Topaz” program: Construction principles and operating regimes

Red Star Scientific-Profuction Organization. Translated from Atomnaya Énergiya, Vol. 70, No. 4, pp. 211–214, April, 1991.     

An algorithm for reconstructing radiation fields in radiation-ecological monitoring of the environment of the megalopolis of Moscow

Moscow Scientific Production Company Radon. Translated from Atomnaya Énergiya, Vol. 72, No. 4, pp. 408–411, April, 1992.     

A probability approach to estimating the safety of a reactor installation

Krasnaya Zvezda Scientific-Designer Bureau. Central Institute of Atomic Energy, All-Union Research Institute of Atomic Energy. Translated from Atomnaya Énergiya, Vol. 74, No. 1, pp. 38–42, January, 1993.