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Calculation of the fuel composition and the thermo-neutronic parameters of the Bushehr’s VVER-1000 reactor during the initial startup and the first cycle using the WIMSD5-B, CITATION-LDI2 and WERL codes

Yashar Rahmani, Ali Pazirandeh, Mohammad B. Ghofrani, Mostafa Sadighi

Ann. Nucl. Energy, vol: 57, num: , 68-83, published: 01 July 2013,


   Nuclear reactor physics.
      Theory and calculation of nuclear reactors and radiation transport.
         Reactors calculations.
            Thermal reactors.

   Nuclear reactor physics.
      Theory and calculation of nuclear reactors and radiation transport.
         Reactors calculations.
            Calculations of fuel isotope composition changes (during fuel cycle and under postirradiation storage) and other fuel cycle parameters. Fuel management calculations. Calculations of radionuclides and actinides build-up.

   Nuclear reactor physics.
      Theory and calculation of nuclear reactors and radiation transport.
         Calculation methods and computer codes.
            Computer codes. Expert systems. Data bases.

   Nuclear reactor physics.
      Neutron physics. Nuclear data.
         Nuclear data for calculations of nuclear reactors, radiation transport and radiation shielding.
            Group, subgroup and other constants for reactor and radiation shielding calculation.

   Nuclear reactor physics.
      Nuclear power. Reliability and safety problems. Engineering problems.
         Thermohydraulics.
            Methods, codes and results of calculational and experimental analysis of temperature fields in materials and constructions, heat transfer and hydrodynamic parameters. Heat transfer intensification.

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