A NUMERICAL STUDY ON FRACTURE TOUGHNESS OF CANDU PRESSURE TUBE

被引:0
|
作者
Keim, Elisabeth [1 ]
Nicak, Tomas [1 ]
Wasiluk, Bogdan [2 ]
机构
[1] AREVA GmbH, Paul Gossen Str 100, D-91052 Erlangen, Germany
[2] Canadian Nucl Safety Commiss, 280 Slater St,POB 1046,Stn B, Ottawa, ON K1P 5S9, Canada
来源
PROCEEDINGS OF THE ASME PRESSURE VESSELS AND PIPING CONFERENCE, 2017, VOL 6A | 2017年
关键词
CANDU reactor; pressure tubes; fracture toughness; fracture constraints; curved compact tension specimen; burst test;
D O I
暂无
中图分类号
TH [机械、仪表工业];
学科分类号
0802 ;
摘要
CANDU pressure tubes carry nuclear fuel and belong to the primary heat transport system. They are fabricated from cold-worked Zr-2.5Nb alloy prone to deuterium ingress under normal operating conditions. Increased hydrogen equivalent concentration and reactor pressure temperature transients result in development of a brittle phase, hydride, changing mechanical behavior. The hydride downgrades fracture toughness properties in the transition region and reduces material ductility. Canadian Nuclear Safety Commission founded a two-phase project to improve understanding of the parameters governing fracture toughness properties and load carrying capacity of Zr-2.5Nb pressure tubes with elevated hydrogen equivalent concentrations. This paper presents preliminary results obtained in the first phase. The fracture behavior of a curved compact tension specimen (CCTS) and a pressure tube burst specimen (PT) with axial through-wall crack used in destructive burst test were studied in details. The intention was to identify any differences between fracture behavior of the CCTS and the PT potentially affecting fracture toughness estimates. The stress and deformation states ahead of the crack front, calculated fracture toughness parameters including J-integral and crack tip opening displacement (CTOD), as well as fracture constraint by means of elastic T-stress have been discussed.
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页数:9
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