1982Nuclear Science and EngineeringRequires access

Application of a Time-Dependent Approach to Burnup Calculations for Pressurized Water Reactor Cores

Y. Bartal, S. Yiftah

Open publisher page 4 citations

Abstract

The feasibility and relative merits of a quasi-time-dependent approach to burnup calculations is investigated. This method, which is shown to be practically equivalent to a true time-dependent approach, uses one iterative level less than the conventional method and is less liable to nonconvergence problems. The method has been formulated using the finite difference form of the neutron diffusion equation and is implemented in a computer code named TDB.Several one- and two-dimensional pressurized water reactor cores were analyzed using both proposed and conventional methods. The calculations show that the proposed method is about twice as fast as the conventional one with a relative accuracy of <5% in material power fractions and critical boron value.

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What this paper is about

The feasibility and relative merits of a quasi-time-dependent approach to burnup calculations is investigated. This method, which is shown to be practically equivalent to a true time-dependent approach, uses one iterative level less than the conventional method and is less liable to nonconvergence problems. The method has been formulated using the finite difference form of the neutron diffusion equation and is implemented in a computer code named TDB.Several one- and two-dimensional pressurized water reactor cores were analyzed using both proposed and conventional methods. The calculations show that the proposed method is about twice as fast as the conventional one with a relative accuracy of <5% in material power fractions and critical boron value.

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Available abstract

The feasibility and relative merits of a quasi-time-dependent approach to burnup calculations is investigated. This method, which is shown to be practically equivalent to a true time-dependent approach, uses one iterative level less than the conventional method and is less liable to nonconvergence problems. The method has been formulated using the finite difference form of the neutron diffusion equation and is implemented in a computer code named TDB.Several one- and two-dimensional pressurized water reactor cores were analyzed using both proposed and conventional methods. The calculations show that the proposed method is about twice as fast as the conventional one with a relative accuracy of <5% in material power fractions and critical boron value.

Key concepts: Burnup, Pressurized water reactor, Nuclear engineering, Diffusion, Nuclear reactor, Neutron transport, Delayed neutron, Computer science

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