Title of article
TRAC-BF1 three-dimensional BWR vessel thermal-hydraulic and ANSYS stress analyses for BWR core shroud cracking
Author/Authors
Feltus، نويسنده , , Madeline Anne; Shoop، نويسنده , , Undine E. Lang، نويسنده ,
Issue Information
روزنامه با شماره پیاپی سال 1998
Pages
17
From page
65
To page
81
Abstract
TRAC-BFl transient analysis for a General Electric boiling water
reactor (BWR/2) was performed for a main steam line break (MSLB) event
and a recirculation line break (RLB) transient to determine the susceptibility
of the core shroud to geometric alteration when intergranular stress corrosion
cracking (lGSCC) is present at the upper H3 and lower H7 core shroud weld
locations. The TRAC-BF I model developed for the MSLB transient utilized a
I-D vessel component model with both main steam lines rupturing at transient
initiation. A detailed ANSYS model was developed to find the forces imposed
at the upper H3 weld positions. The TRAC-BFl model developed for the RLB
transient utilized a 3-D four azimuthal sector vessel component. FORTRAN
programs were developed to calculate the forces at the lower (H7) weld location.
The results of both transients followed the typical thermal-hydraulic
behavior pattern expected during the transients; however, the extreme forces
exerted on the core shroud could displace or rotate the shroud during these
two postulated transients. Such shroud movement could impede control rod
insertion and impair the safe shut down of the reactor. The TRAC-BF 1
pressure response and the ANSYS lift forces demonstrated that when IGSCC
is present at the upper H3 core shroud weld, a lift force of 95 925 Pa (13.91 psi)
is generated during the double MSLB transient which is great enough to
overcome the weight of the vessel internals resting on the core shroud, causing
the core shroud to lift. Additionally, the finite element ANSYS stress analysis
demonstrated that when IGSCC is not present in the upper core shroud weld,
stresses of 1757.3 MPa (254880.0 psi) are induced in the filler material during a
main steam line break. This is great enough to overcome the ultimate strength
of 1723.7 Ma (250000 psi) of the filler material and cause failure of the weld.
The TRAC-BFl RLB transient results determined that during the RLB event
a force of 401.7 kN (90 3061bf) is generated at the lower H7 core shroud weld
which is great enough to cause displacement of a segment of the core shroud
support structure when IGSCC is present.
Journal title
Annals of Nuclear Energy
Serial Year
1998
Journal title
Annals of Nuclear Energy
Record number
405190
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