PLASMA AND NEUTRON PROCESSES SIMULATION IN A FISSION-FUSION SYSTEM

					        XXXVIII international conference on plasma physics and CF, February 14 – 18, 2011, Zvenigorod.



PLASMA AND NEUTRON PROCESSES SIMULATION IN A FISSION-FUSION SYSTEM
                 BASED ON THE GAS DYNAMIC TRAP
        *
         S.A. Brednikhin, *L.V. Kardapoltsev, A.A. Ivanov, V.V. Prikhodko, *S.A. Frolov,
                                          D.V. Yurov
     Budker Institute of Nuclear Physics SB RAS, Novosibirsk, Russia
     *
       Nuclear Safety Institute RAS (Novosibirsk branch), Novosibirsk, Russia

   Long-lived fission products utilization is a highly important problem for the present nuclear
reactor technology. It is possible to use sub-critical fission systems with neutron drivers to solve
this problem. Neutron source parameters are determinative for fuel incineration rate and prevailing
type of nuclear reactions in the blanket of such systems. Numerical model of sub-critical system
with a GDT-based neutron driver development is conducted in BINP jointly with NSI RAS.
Machine compactness, spatial extension of the source, neutron flux spatial scaling possibility and
improved energy release per neutron are the advantages of the proposed system in comparison with
similar systems with ADS-driven neutron sources [1,2].
   Neutron source parameters calculation was conducted by zero-dimensional model of plasma
evolution in the gas dynamic trap (BINP). Temperature and density dynamics is under consideration
in the framework of the model in accordance with processes described in [3]. Fast ions distribution
function is also taken into account in the model. It is evaluated through the one-dimensional kinetic
equation taking into consideration fast ion charge exchange with neutral heating beams,
deceleration and angular scattering on the warm plasma components. Furthermore, fast ions density
and neutron flux intensity distributions in relation to the position along the trap axis can be
evaluated by the means of the numerical model.
   Reactor blanket characteristics calculation was implemented by NMK – simulation code of
neutron processes in sub-critical systems (NSI RAS). The main advantages of the code are
functional extensibility and capacity for blanket heat generation calculation. Computation results
were tested with the help of “International handbook of evaluated criticality safety benchmark
experiments” (ICSBEP).
   Neutron flux characteristics from the GDT device in dependence on the parameters of the
machine will be presented in the report, as well as neutron processes simulation results for the
EFIT-based blanket (European Facility for Industrial Transmutation) with plasma drivers of
different configurations.
References
[1]. Noack K., Rogov A., Anikeev A.V., Ivanov A.A., Kruglyakov E.P., Tsidulko Yu.A. The
     GDT-based neutron source as a driver of a minor actinides burner. Annals of Nuclear Energy,
     2008, 35, 1216–1222
[2]. Anikeev A.V., Bagryansky P.A., Ivanov A.A., Kruglyakov E.P., Tsidulko Yu.A., Noack K.
     High-intense fusion neutron source as driver in a sub-critical burner of radioactive wastes.
     XXXVI Zvenigorod international conference on plasma physics and controlled fusion
     proceedings, 2009, 39
[3]. Mirnov V.V., Ryutov D.D., Gas Dynamic Trap. Problems of atomic science and technology
     (“Nuclear fusion” topic),I(5), 1980, 57




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posted:4/30/2011
language:English
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