Method of obtaining fusion reactor experimental covering module neutronics parameters

Abstract

The invention discloses a method of obtaining fusion reactor experimental covering module neutronics parameters. The method of obtaining fusion reactor experimental covering module neutronics parameters adopts a two-step method. The first step, according to axial geometry features of a fusion reactor experimental covering module, portions which are the same in the geometry and materials in an axial direction can be cut in an identical area. The covering module can be cut into a plurality of model lattice cells. Characteristic lines can be utilized to calculate a module to solve a neutron-transport equation in each lattice cell to obtain a thin crowd neutron-flux distribution. The obtained neutron-flux distribution can be utilized in each lattice cell, and homogenization modules can be adopted to be in homogenization to obtain thick crowd section parameters according to the weight of influx volume. The second step, the thick crowd section parameters of each model lattice cell can be used as known parameters to calculate the neutron-flux distribution of the fusion reactor experimental covering module in the entire fusion reactor experimental covering modules, wherein the thick crowd section parameters of each model lattice cell are obtained for the first step. Further, each item neutronics parameters can be calculated. The method of obtaining fusion reactor experimental covering module neutronics parameters has the advantages of being high in efficiency and precision so as to provide a result with a guiding and reference significance for a constructing design of a fusion reactor.

Description

technical field [0001] The invention relates to the field of neutronics analysis of a fusion reactor experimental envelope module Test Blanket Module (TBM), in particular to a method for obtaining neutronics parameters of a fusion reactor experimental envelope module. Background technique [0002] A fusion reactor is a device that uses controlled nuclear fusion to continuously output energy. In the current design, the main structure of the fusion reactor is the cladding, which is composed of hundreds of individual cladding modules (TBMs). TBM neutron flux distribution and tritium production ratio (TBR), tritium production rate, neutron irradiation damage DPA, gas swelling and other related parameters are called neutronic parameters, and the process of obtaining these parameters is called neutronic analysis. Scientific analysis is of great significance to the design and construction of fusion reactors. Since the fusion reactor is still under design, the TBM neutronics analy...

AI Technical Summary

Problems solved by technology

Therefore, the results of the MCNP program are closely related to the number of statistical samples, and a large number of neutrons must be invested to obtain more accurate results, which makes the calculation efficiency of the MCNP program very low

At present, the construction of fusion reactors and the exploration and analysis of the physical mechanism in the early stage often require a large number of neutronics analysis and calculations. Under the current calculation conditions, it is still very time-consuming to use the MCNP program to perform these calculations; It is difficult to obtain the fine spatial distribution and angular distribution of neutron flux in the object

Images