Published February 2020 | Version v1
Journal article

Buffering effect analysis for secondary supports in reactor vessel internals under assumption accident of core drop

  • 1. China Nuclear Power Design Co., Ltd., Shenzhen, Guangdong (China)
  • 2. Nuclear and Radiation Safety Center, Beijing (China)

Description

To research the buffering effect of secondary supports in reactor vessel internals under the assumption accident of core drop (core barrel broken down), a buffering effect analysis of secondary supports is performed, based on the technology of water buffering and mechanical buffering. In this paper, the process for core drop is numerically modeled, and the core barrel movement mechanism under different vertical gap, coolant temperature and initial flow rate is analyzed based on Fluent. The impact process in the end of core drop is analyzed and the water buffering effect of the secondary support is studied based on LS-DYNA. The analysis results show that, using the technology of water buffering and mechanical buffering, the secondary supports can bearing the impact energy of the core drop, and the coolant can buffer most of the impact energy. The buffering effect of secondary supports in this paper is better than that of the traditional support structure, to ensure the integrity of the reactor pressure vessel (RPV). (authors)

Additional details

Identifiers

Publishing Information

Journal Title
Nuclear Power Engineering
Journal Volume
41
Journal Issue
2
Journal Page Range
p. 54-58
ISSN
0258-0926

INIS

Country of Publication
China
Country of Input or Organization
China
INIS RN
55086364
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Descriptors DEI
PRESSURE VESSELS; REACTOR ACCIDENTS; REACTOR CORES; SUPPORTS; WATER
Descriptors DEC
ACCIDENTS; CONTAINERS; HYDROGEN COMPOUNDS; MECHANICAL STRUCTURES; OXYGEN COMPOUNDS; REACTOR COMPONENTS

Optional Information

Notes
7 figs., 1 tab., 2 refs.; http://dx.doi.org/10.13832/j.jnpe.2020.02.0054