Combined Neutronics Calculation of the Radiation Protection for a Nuclear Reactor with Heavy Liquid-Metal Coolant
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The problem of calculating a model of the radiation protection of a monoblock reactor, having a fast neutron spectrum and cooled by a eutectic lead-bismuth alloy, by a combined method using the CADIS methodology is examined. A deterministic calculation of the adjoint problem is performed by the method of characteristics, ensuring the smoothness of the solution. An algorithm for selecting the nodes of the weight window grid is presented for the many-group problem. The results of the neutron flux density distribution for the computational domain are described. A statistical error of 7% is obtained, confirming the methodological reliability of the spatial distribution of the neutron flux density in the Monte Carlo method.
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- 2.I. R. Suslov, I. A. Lyamtsev, and S. V. Chernov, “Hybrid method of calculation based on the CADIS variance reduction scheme,” Izv. Vyssh. Uchebn. Zaved. Yad. Energet., No. 2, 71–79 (2013).Google Scholar
- 3.MCNP – a General Monte Carlo N-Particle Transport Code, Vers. 4B, LA-12625-M (1997).Google Scholar
- 4.I. R. Suslov, “MCCG3D – 3D discrete ordinates transport code for unstructured grid/state of art and future development,” in: Neutronics-96, FEI, Obninsk (1996), p. 162.Google Scholar
- 6.MCNP – a General Monte Carlo N-Particle Transport Code, Vol. II, User’s Guide, Vers. 5, LA (2003).Google Scholar