A probabilistic fracture mechanics (PFM) code, PRAISE-CANDU 1.0, has been developed under a software quality assurance (QA) program in full compliance with Canadian Standards Association (CSA) N286.7-99, and was initially released in June 2012 and officially approved for use in August 2013. Extensive verification and validation has been performed on PRAISE-CANDU 1.0 for the purpose of software QA. This paper presents the fatigue benchmarking against NURBIM (nuclear risk based inspection methodology for passive components) fatigue cases between PRAISE-CANDU 1.0 and six other PFM codes. This benchmarking is considered to be an important element of the validation of PRAISE-CANDU. Excellent agreement is observed in spite of the differences between the codes. The comparison of the predicted leak probability at the 40th year shows that PRAISE-CANDU not only captures the same trend but also bounds (higher predicted failure probability) the majority of the NURBIM results. In addition to the leak probability, the rupture probability, and uncertainty analysis, which were not reported in the NURBIM Project, are also calculated with PRAISE-CANDU and presented.

References

References
1.
Canadian Standards Association
,
1999
, “
Quality Assurance of Analytical, Scientific and Design Computer Programs for Nuclear Power Plants
,” Report No. CSA N286.7-99.
2.
Brickstad
,
B.
,
Dillstrom
,
P.
,
Schimpfke
,
T.
,
Chapman
,
O. J. V.
,
Cueto-Felgueroso
,
C.
, and
Bell
,
C. D.
,
2004
, “
Project NURBIM (Nuclear RI-ISI Methodology for Passive Components), Benchmarking of Structural Reliability Models and Associated Software
,”
ASME
Paper No. PVP2004-2551.
3.
Schimpfke
,
T.
,
2004
, “
WP-4, Review and Benchmarking of SRMs and Associated Software. Appendix B, Fatigue Benchmark Study
,” NURBIM Report No. D4.
4.
Bishop
,
B.
, and
Anderson
,
R.
,
2008
, “
NURBIM Fatigue Benchmarking of SRRA Code for Risk-Informed ISI
,”
CNSI&JRC Workshop on Risk-Informed Piping Integrity Management
, Madrid, Spain, June 2–4.
5.
Duan
,
X.
,
Wang
,
M.
, and
Kozluk
,
M. J.
,
2011
, “
Comparison of PRO-LOCA 2009 With WinPRAISE 2007 for Estimating Rupture Probability of Dissimilar Metal Weld Susceptible to PWSCC
,”
Proceedings of 19th International Conference of Nuclear Engineering (ICONE19)
,
Makuhari, Japan
, May 16–20, Paper No. ICONE19-43921.
6.
Harris
,
D. O.
,
Lim
,
E. Y.
, and
Dedhia
,
D.
,
1981
, “
Probability of Pipe Fracture in the Primary Coolant Loop of a PWR Plant, Volume 5: Probabilistic Fracture Mechanics Analysis
,” U.S. Nuclear Regulatory Commission, Volume 5, Washington, D.C., Report No. NUREG/CR-2189.
7.
Lim
,
E. Y.
,
1981
, “
Probability of Pipe Fracture in the Primary Coolant Loop of a PWR Plant, Volume 9: PRAISE Computer Code User's Manual
,” U.S. Nuclear Regulatory Commission, Volume 5, Washington, D.C., Report No. NUREG/CR-2189.
8.
Wang
,
M.
,
2013
, “
Benchmark PRAISE-CANDU 1.0 with xLPR 1.0
,”
ASME
Paper No. PVP2013-98010.10.1115/PVP2013-98010
9.
OECD NEA
,
2011
, “
CODAP-Component Operational Experience, Degradation and Ageing Programme Database.
” Available at: https://www.oecd-nea.org/codap.
10.
U.S. Nuclear Regulatory Commission
,
1999
, “
Technical Elements of Risk-Informed Inservice Inspection Programs for Piping
,” Draft Report No. NUREG-1661.
11.
The Nuclear Regulators' Working Group Task Force on Risk-Informed Inservice Inspection
,
2004
, “
Report on the Regulatory Experience of Risk-Informed Inspection of Nuclear Power Plant Components and Common Views
,” Report No. EUR 21320 EN.
12.
European Network for Inspection Qualification
,
2007
, “
Recommended Practice 9: Verification and Validation of Structural Reliability Models and Associated Software to Be Used in Risk-Informed In-Service Inspection Programmes
,” ENIQ Report No. 30, EUR Report No. 22228 EN.
13.
International Atomic Energy Agency
,
2010
, “
Risk-Informed In-Service Inspection of Piping Systems of Nuclear Power Plants: Process, Status, Issues and Development
,” IAEA Nuclear Energy Series No. NP-T-3.1.
14.
Moolayil
,
T. M.
,
2007
, “
Mitigation of Degradation of High Energy Secondary Cycle Piping due to FAC and Life Management in Indian NPP's
,”
Second International Symposium on Nuclear Power Plant Life Management
,
Shanghai, China
, October 15–18.
You do not currently have access to this content.