The integrity of a reactor pressure vessel (RPV) related to pressurized thermal shocks (PTSs) has been extensively studied. This paper introduces the method of using fracture mechanics for the integrity analysis of a RPV subjected to PTS transients. A 3-D finite element (FE) model is used to perform thermal and fracture mechanics analyses by considering both elastic and elastic–plastic material models. The results show that the linear elastic analysis leads to a more conservative result than the elastic–plastic analysis. The variation of the T-stress and Q-stress (crack tip constraint loss) of a surface crack in a RPV subjected to PTSs is studied. A shallow crack is assumed in the RPV and the corresponding constraint effect on fracture toughness of the material is quantified by the K–T method. The safety margin of the RPV is larger based on the K–T approach than based only on the K approach. The J–Q method with the modified boundary layer formulation (MBL) is used for the crack tip constraint analysis by considering elastic–plastic material properties. For all transient times, the real stress is lower than that calculated from small scale yielding (SSY) due to the loss of crack tip constraint.
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February 2015
Research-Article
Investigation on Constraint Effect of a Reactor Pressure Vessel Subjected to Pressurized Thermal Shocks
Guian Qian,
Guian Qian
1
Laboratory for Nuclear Materials,
Nuclear Energy and Safety Department,
e-mail: guian.qian@psi.ch
Nuclear Energy and Safety Department,
Paul Scherrer Institute
,Villigen 5232
, Switzerland
e-mail: guian.qian@psi.ch
1Corresponding author.
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Markus Niffenegger
Markus Niffenegger
Laboratory for Nuclear Materials,
Nuclear Energy and Safety Department,
Nuclear Energy and Safety Department,
Paul Scherrer Institute
,Villigen 5232
, Switzerland
Search for other works by this author on:
Guian Qian
Laboratory for Nuclear Materials,
Nuclear Energy and Safety Department,
e-mail: guian.qian@psi.ch
Nuclear Energy and Safety Department,
Paul Scherrer Institute
,Villigen 5232
, Switzerland
e-mail: guian.qian@psi.ch
Markus Niffenegger
Laboratory for Nuclear Materials,
Nuclear Energy and Safety Department,
Nuclear Energy and Safety Department,
Paul Scherrer Institute
,Villigen 5232
, Switzerland
1Corresponding author.
Contributed by the Pressure Vessel and Piping Division of ASME for publication in the JOURNAL OF PRESSURE VESSEL TECHNOLOGY. Manuscript received September 21, 2013; final manuscript received July 10, 2014; published online September 15, 2014. Assoc. Editor: Albert E. Segall.
J. Pressure Vessel Technol. Feb 2015, 137(1): 011204 (7 pages)
Published Online: September 15, 2014
Article history
Received:
September 21, 2013
Revision Received:
July 10, 2014
Citation
Qian, G., and Niffenegger, M. (September 15, 2014). "Investigation on Constraint Effect of a Reactor Pressure Vessel Subjected to Pressurized Thermal Shocks." ASME. J. Pressure Vessel Technol. February 2015; 137(1): 011204. https://doi.org/10.1115/1.4028017
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