Calculation of seismic performance of nuclear containment vessel structure under design base earthquake

In order to obtain frequencies and modal shapes of a nuclear containment vessel, the computational analyses have been carried out through free structure finite element analysis software. The finite element model of the vessel is built with shell element and solved by the type of the dynamics frequency solver. Results show that mainly deformation area is on the vessels cylindrical shell and the maximum displacements occur at its center. Compared with the design validation values, the frequencies obtained are a little lower. It may be because that the model built here is a completely vessel shell without any hatches or attachments. It is provided that a reliable method of computational structural analyses for the nuclear containment without commercial software cost.

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Investigation of Mechanical Properties and Ductile-Brittle Transition Behaviors of SA738Gr.B Steel Used as Reactor Containment

Key Engineering Materials ◽

10.4028/www.scientific.net/kem.795.66 ◽

2019 ◽

Vol 795 ◽

pp. 66-73

Author(s):

Ya Lin Zhang ◽

Hu Hui

Keyword(s):

Fracture Toughness ◽

Master Curve ◽

Steel Plate ◽

Reference Temperature ◽

Impact Performance ◽

Brittle Transition ◽

Containment Vessel ◽

Master Curve Method ◽

Nuclear Containment ◽

Curve Method

The low temperature tensile properties, Charpy-V notch impact performance and fracture toughness of SA738Gr.B steel plate for domestic CAP1400 containment vessel were tested. On this basis, the reference temperature T0 of the master curve method was obtained. The fracture toughness distribution of the steel in the whole ductile-brittle transition zone is predicted and its applicability is verified by the theoretical basis of the master curve method. The results show that the reference temperature of SA738Gr.B steel master curve method is-123.6 °C. The master curve method is appropriate for SA738Gr.B steel with domestic nuclear containment vessel.

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Structural analysis of aircraft impact on a nuclear containment vessel and associated structures

Nuclear Engineering and Design ◽

10.1016/0029-5493(70)90153-6 ◽

1970 ◽

Vol 11 (2) ◽

pp. 295-307 ◽

Cited By ~ 8

Author(s):

H.T.Y. Yang ◽

D.A. Godfrey

Keyword(s):

Structural Analysis ◽

Containment Vessel ◽

Nuclear Containment

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Three-Dimensional Finite Element Analysis of a Scale Model Nuclear Containment Vessel

Journal of Pressure Vessel Technology ◽

10.1115/1.3264792 ◽

1986 ◽

Vol 108 (3) ◽

pp. 320-329

Author(s):

G. Derbalian ◽

G. Fowler ◽

J. Thomas

Keyword(s):

Finite Element Analysis ◽

Finite Element ◽

Ultimate Strength ◽

Three Dimensional ◽

Scale Model ◽

Element Analysis ◽

Containment Vessel ◽

Nuclear Containment ◽

Dimensional Finite Element ◽

Three Dimensional Finite Element

Current design procedures for nuclear containment vessels are based on elastic analyses. Though such techniques are adequate under normal operating conditions, if the potential risks associated with extreme environments or accident conditions are to be assessed, knowledge of the ultimate capacity of the containment structure is essential. A key technical question is whether penetrations, such as personnel hatches, weaken the containment structure. In this paper, the maximum pressure sustained by a scale model, steel, nuclear containment vessel with a penetration is determined using a three-dimensional finite element analysis. To assess containment strength, a clean shell is analyzed in closed form for its ultimate strength, and the solution is then compared with finite element results for a structure that has a penetration. The comparison shows that the personnel hatch penetration does not reduce the ultimate strength of the containment structure. In this paper, it is assumed that the materials have no flaws and welded joints are perfectly bonded. Cracks in the structure, which would degrade its strength, are not considered.

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