DocumentCode
2941518
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
fYear
2011
fDate
25-28 March 2011
Firstpage
1
Lastpage
4
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;
fLanguage
English
Publisher
ieee
Conference_Titel
Power and Energy Engineering Conference (APPEEC), 2011 Asia-Pacific
Conference_Location
Wuhan
ISSN
2157-4839
Print_ISBN
978-1-4244-6253-7
Type
conf
DOI
10.1109/APPEEC.2011.5749124
Filename
5749124
Link To Document