Abstract
A tritium breeding blanket (TBB) is an essential component in a fusion reactor, which has functions of tritium breeding, energy generation and neutron shielding. Tritium breeding ratio (TBR) is a key parameter to evaluate whether the TBB could produce enough tritium to achieve tritium self-sufficiency (TBR > 1) for a fusion reactor. Current codes or software struggle to meet the requirements of high efficiency and high automation for neutronic optimization of the TBB. In this paper, the multiphysics coupling and automatic neutronic optimization method study for a solid breeder TBB is performed, and a corresponding code is developed. A typical module of China fusion engineering test reactor (CFETR) helium cooled ceramic breeder (HCCB) TBB was selected, and a 3D neutronics model of an initial scheme is developed. The automatic neutronic optimization was performed by using the developed code for verification. Results indicate that the TBR could increase from 1.219 to 1.282 (~5.17% improvement), and that the maximum temperature of each type of material in the optimized scheme is below the allowable temperature. It is of great scientific significance and engineering value to explore and study the algorithm for automatic neutronic optimization and the code development of the TBB.
Highlights
The tritium breeding blanket (TBB) is an essential component to achieve tritium production, energy generation and extraction in a fusion reactor
Tritium self-sufficiency is a significant goal, and the tritium breeding ratio (TBR) is a key parameter to evaluate whether the TBB can produce enough tritium to achieve tritium self-sufficiency for fusion reactor, which can be calculated as follows Equation (1)
Energies 2021, 14, x FOR PEER REVIEW Using programing in Fortran 2013, the multiphysics coupling and neutronics automatic optimization code was developed on Visual Studio 2012
Summary
The tritium breeding blanket (TBB) is an essential component to achieve tritium production, energy generation and extraction in a fusion reactor. The TBR of the fusion reactor can be impacted by a number of factors, including the geometries (the opening ports to install the corresponding heating and diagnostic equipment [1,2], and a heterogeneous model of the blanket [3]), materials (type, density, enrichment), nuclear libraries (uncertainty), and neutron transport codes. The TBR of the fusion reactor can be impacted by a number of factors, oinf -14 cluding the geometries (the opening ports to install the corresponding heating and diagnostic equipment [1,2], and a heterogeneous model of the blanket [3]), materials (type, density, enrichment), nuclear libraries (uncertainty), and neutron transport codes (uncerta(iunntcye).rtMaienatnyw). The discretization equation can be solved by using the chase-after method of tridiagonal equations, which is expressed as follows:
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