Published August 1999 | Version v1
Journal article Metadata-only

Nonlinear dynamic analysis under LOCA condition for reactor system

Creators

  • 1. Nuclear Power Inst. of China, Chengdu (China)

Description

The hypothetical loss-of-coolant accident (LOCA) in the primary piping is assumed in the design of Qinshan II reactor system. This accident causes transient pressure variation of the coolant and induces dynamic hydraulic loads on reactor components. The author describes the non-linear dynamic analysis procedure of reactor system including the engineering method for nonlinear factors, the establishment of the nonlinear dynamic model and the nonlinear dynamic analysis method. The generation and the application of the LOCA dynamic response for the system are also presented

Additional details

Publishing Information

Journal Title
Nuclear Power Engineering
Journal Volume
20
Journal Issue
4
Journal Page Range
p. 342-347
ISSN
0258-0926

INIS

Country of Publication
China
Country of Input or Organization
China
INIS RN
31007260
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Descriptors DEI
LOSS OF COOLANT; MATHEMATICAL MODELS; NONLINEAR PROBLEMS; NUCLEAR POWER PLANTS; QINSHAN-2 REACTOR; REACTOR COMPONENTS
Descriptors DEC
ACCIDENTS; ENRICHED URANIUM REACTORS; NUCLEAR FACILITIES; POWER PLANTS; POWER REACTORS; PWR TYPE REACTORS; REACTOR ACCIDENTS; REACTORS; THERMAL POWER PLANTS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS