Title :
Analysis and Comparison of Typical Solutions for Neutron Dynamic Equation with Six-Group Delayed Neutron
Author :
Ma, Jin ; Gao, Ming-ming ; Ma, Yong-guang
Author_Institution :
Sch. of Control Sci. & Comput. Eng., North China Electr. Power Univ., Baoding, China
Abstract :
Several typical solutions for point-reactor neutron dynamic equation were introduced, which includes Gear method, Decoupling method, Taylor polynomials method, Prompt jump approximate, as well as some improved methods, such as SCM method, Taylor polynomial integral method etc. The calculation ideas and equations or iterative formula of these solutions were analyzed in the paper, then the comparison is done to show their advantages and disadvantages.
Keywords :
fission reactor core control; neutron diffusion; nuclear power stations; polynomial approximation; SCM method; Taylor polynomials method; decoupling method; gear method; point-reactor neutron dynamic equation; prompt jump approximate; six-group delayed neutron; Gears; Inductors; Kinetic theory; Mathematical model; Neutrons; Polynomials;
Conference_Titel :
Power and Energy Engineering Conference (APPEEC), 2011 Asia-Pacific
Conference_Location :
Wuhan
Print_ISBN :
978-1-4244-6253-7
DOI :
10.1109/APPEEC.2011.5749124
