Aseismatic design of pipings for nuclear power plants

Journal Article · Thu Mar 01 04:00:00 EST 1973 · Haikan Gijutsu, v. 15, no. 3, pp. 157-170

OSTI ID:4313151

Akino, K; Kato, M; Tamura, S

Every constituent of nuclear power plants is classified into three ranks of A, B, and C from the point of safety. Aseismatic design method is adopted corresponding to the importance of each constituent. ASME Section III classifies the piping into Class-1 and Class-2. The design of the Class-1 piping is applied to A class piping, and that of Class-2 piping is applied to B class one. The ASME Section III defines five conditions of Design, Normal, Upset, Emergency and Faulted for the Class-1 piping components, and decides allowable stress corresponding to the sort of the stress. For the dynamical analysis of pipings, there is the method to treat the pipings as continuuan (DINAPS) and there is the method to treat the pipings as models consisting of material points and elastic rods. The dynamic analysis contains eigenvalue analysis and earthquake response analysis. The eigenvalue analysis of complex structures is performed by using a large matrix method and transfer matrix method. A code DIANA III, which Japan Atomic Power Corporation has developed, uses the transfer matrix method, which is described. The earthquake response analysis is classified into time-history analysis and modal analysis is used for the response analysis of pipings. (JA)

• Research Organization: Japan Atomic Power Co., Tokyo
• NSA Number: NSA-29-023635
• OSTI ID: 4313151
• Journal Information: Haikan Gijutsu, v. 15, no. 3, pp. 157-170, Journal Name: Haikan Gijutsu, v. 15, no. 3, pp. 157-170; ISSN HAGIB
• Country of Publication: Japan
• Language: Japanese

Related Subjects

*NUCLEAR POWER PLANTS-- PIPELINES
*PIPELINES-- SEISMIC EFFECTS
ANALYTICAL SOLUTION
D CODES
EARTHQUAKES
MATRICES
MECHANICAL VIBRATIONS
N79200* --Reactors--Reactor Components & Accessories
PIPES
REACTOR COOLING SYSTEMS
REACTOR SAFETY
STRESS ANALYSIS
THERMAL STRESSES