atw 2019-02

atw Vol. 64 (2019) | Issue 2 ı February
ENVIRONMENT AND SAFETY 94
| | Fig. 8.
Line #01 Maximum resultant moment for load case 100.
| | Fig. 9.
Line #01 Maximum stress for load case 100.
Load Case Title Max. Stress Ratio Location Point
100 Operating Weight 0.982 0
101 Thermal Expansion 0.031 5
300 Earthquake RG 1.60 0.094 0
400 Operating Weight + Earthquake 0.363 0
401 Operating Weight + Thermal 0.605 0
| | Tab. 4.
Summary of the Results for Line#03.
piping respectively. Finally, a table
is also included which summarizes
the results for complete line. The
highest stress points for load case-
100 have been shown in Table 2.
5.2 From Discharge of SI Pump
to the Penetration
Unlike line #01, here all loading cases
have not been tabulated separately.
Only a table is included which
summarizes the results for the
complete line. Table 3 includes the
maximum stress ratio for each case
and its point of location.
5.3 From Penetration to RCS
Header
Like line#02, only a table is included
which summarizes the results for the
complete line. Table 4 includes the
maximum stress ratio for each case
and its point of location.
6 Conclusions
The analysis of the safety injection
system on Peps, stress analysis tool,
has been performed by dividing it into
three lines. The first line is from
refueling water storage tank (RWST)
to the suction of safety injection (SI)
pump. The second line is from discharge
of SI pump to the penetration
while the third line starts from the
penetration and ends at reactor coolant
system (RCS) header. The analysis
of all these lines has been performed
using the software. The series of steps
followed while working on Peps
included cases definition (both load
cases and combination cases), preparation
of input file, modeling on
Peps, running the simulations and
generating the stress reports. The
preparation of an input file consists of
different cards.
The analysis of a line consisted of
different load and combination cases.
Each case was analyzed and a stress
report was generated. The stress
report included the determination of
displacements, loads, moments and
stress ratios. All the values of stress
ratio were found out to be very less
than unity. This analysis confirmed
that piping system stresses were
within the limits specified by the
ASME code.
Acknowledgement
Authors are grateful to Mr. Rizwan
Mahmood, Mr. Amjad Ali Amjad and
administration of Advanced Computational
Reactor Engineering Lab for
their kind support.
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Authors
Mazhar Iqbal
Agha Nadeem
Tariq Najam
Kamran Rasheed Qureshi
Waseem Siddique
Rustam Khan
Pakistan Institute of Engineering
and Applied Sciences
Nilore, Islamabad, Pakistan
Environment and Safety
Piping Stress Analysis of Safety Injection System of Typical PWR Power Reactor ı Mazhar Iqbal, Agha Nadeem, Tariq Najam, Kamran Rasheed Qureshi, Waseem Siddique and Rustam Khan