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Neutronic analysis of a moderated (D, T) fusion driven hybrid blanket

Yapici H., Akansu S.O., Ozceyhan V.

Ann. Nucl. Energy, vol: 27, num: 13, 1237-1244, published: 01 September 2000, GB


   Nuclear reactor physics.
      Nuclear power. Reliability and safety problems. Engineering problems.
         Fuel cycle.
            Fissionable and radioactive materials control. Physico-technical and non-technical aspects. Safety and nonproliferation guaranties.

   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.
         Reactors calculations.
            Calculations of neutron and gamma distributions, power generation, reaction rates, residual radioactivity and residual power generation.

   Nuclear reactor physics.
      Theory and calculation of nuclear reactors and radiation transport.
         Reactors calculations.
            Hybrid systems and blankets of thermonuclear and hybrid reactors.

   Plasma Physics (including Thermonuclear Fusion).
      Magnetic plasma confinement. (including fusion reactions)
         Thermonuclear reactors (Fusion reactors).
            Blanket.

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