The stress intensity factor (SIF) solutions for subsurface flaws near the free surfaces of components, which are known to be important in engineering applications, have not been provided yet. Thus, in this paper, SIF solutions for subsurface flaws near the free surfaces in flat plates were numerically investigated based on the finite element analyses. The flaws with aspect ratios a/ℓ = 0.0, 0.1, 0.2, 0.3, 0.4, and 0.5, the normalized ratios a/d = 0.0, 0.1, 0.2, 0.4, 0.6, and 0.8, and d/t = 0.01 and 0.10 were taken into account, where a is the half flaw depth, ℓ is the flaw length, d is the distance from the center of the subsurface flaw to the nearest free surface, and t is the wall thickness. Fourth-order polynomial stress distribution in the thickness direction was considered. In addition, the developed SIF solutions were incorporated into a Japanese probabilistic fracture mechanics (PFM) code, and PFM analyses were performed for a Japanese reactor pressure vessel (RPV) containing a subsurface flaw near the inner surface. The PFM analysis results indicate that the obtained SIF solutions are effective in engineering applications.

References

References
1.
Newman
,
J. C.
, and
Raju
,
I. S.
,
1983
, “
Stress-Intensity Factor Equations for Cracks in Three-Dimensional Finite Bodies
,” Fracture Mechanics: Fourteenth Symposium—Volume I: Theory and Analysis, Los Angeles, CA, June 30–July 2, Paper No.
ASTM STP 791
.
2.
Isida
,
M.
, and
Noguchi
,
H.
,
1984
, “
Tension of a Plate Containing an Embedded Elliptical Crack
,”
Eng. Fract. Mech.
,
20
(
3
), pp.
387
408
.
3.
Shiratori
,
M.
,
Ogawa
,
T.
, and
Nishijima
,
A.
,
1992
, “
Analysis of Stress Intensity Factor for Embedded Crack Subjected to Arbitrarily Distributed Surface Stresses: Analysis and Application of Influence Coefficients for Flat Plates With an Embedded Elliptical Crack
,”
Trans. Jpn. Soc. Mech. Eng. Ser. A
,
58
(
545
), pp.
48
52
.
4.
Miyazaki
,
K.
,
Iwamatsu
,
F.
,
Nakanishi
,
S.
, and
Shiratori
,
M.
,
2006
, “
Stress Intensity Factor Solution for Subsurface Flaw Estimated by Influence Function Method
,”
ASME
Paper No. PVP2006-ICPVT-11-93138.
5.
ASME
,
2015
, “
ASME B&PV Code Section XI, Rules for in-Service Inspection of Nuclear Power Plant Components
,” American Society of Mechanical Engineers, New York, Standard No. ASME BPVC XI-2015.
6.
JSME
,
2012
, “
Codes for Nuclear Power Generation Facilities—Rules on Fitness-for-Service for Nuclear Power Plants
,” Japan Society of Mechanical Engineers, Tokyo, Japan, Standard No. JSME S NA1-2012.
7.
Williams
,
P. T.
,
Dickson
,
T. L.
, and
Yin
,
S.
,
2012
, “
Fracture Analysis of Vessels-Oak Ridge FAVOR, v12.1, Computer Code: Theory and Implementation of Algorithms, Methods, and Correlations
,” Oak Ridge National Laboratory, Oak Ridge, TN, Report No.
ORNL/TM-2012/567
.
8.
Masaki
,
K.
,
Nishikawa
,
H.
,
Osakabe
,
K.
, and
Onizawa
,
K.
,
2011
, “
User's Manual and Analysis Methodology of Probabilistic Fracture Mechanics Analysis Code Pascal3 for Reactor Pressure Vessel (Contract Research)
,” Japan Atomic Energy Agency, Ibaraki, Japan, Report No. JAEA-Data/Code 2010-033 (in Japanese).
9.
Doi
,
H.
,
Nakamura
,
H.
,
Gu
,
W.
,
Shim
,
D.
, and
Wilkowski
,
G.
,
2014
, “
Verification Analyses for Newly Developed Automatic 3D Finite Element Crack Propagation System
,”
ASME
Paper No. PVP2014-28602.
10.
Dassault Systèmes Simulia Corp.,
2012
,
ABACUS/CAE User's Manual
, Version 6.12,
Dassault Systèmes Simulia Corp
,
Providence, RI
.
11.
Dassault Systèmes Simulia Corp.,
2012
,
ABACUS User's Manual
, Version 6.12,
Dassault Systèmes Simulia Corp
,
Providence, RI
.
12.
Lu
,
K.
,
Katsuyama
,
J.
,
Uno
,
S.
, and
Li
,
Y.
, 2017, “
Probabilistic Fracture Mechanics Analysis Models for Japanese Reactor Pressure Vessels
,”
ASME
Paper No. PVP2017-66003.
13.
JAPEIC
,
1992
, “
Investigation Report of Reliability Verification Test for Weld Heat-Affected Zone
,” Japan Power Engineering and Inspection Corporation, Tokyo, Japan, Report No. JPEIC-1992 (in Japanese).
14.
Katsuyama
,
J.
,
Nishikawa
,
H.
,
Udagawa
,
M.
,
Nakamura
,
M.
, and
Onizawa
,
K.
,
2013
, “
Assessment of Residual Stress Due to Overlay-Welded Cladding and Structural Integrity of a Reactor Pressure Vessel
,”
ASME J. Pressure Vessel Technol.
,
135
(
5
), p.
051402
.
15.
JEA
,
2007
, “
Method of Surveillance Tests for Structural Materials of Nuclear Reactors
,” Japan Electric Association, Tokyo, Japan, Report No. JEAC4201-2007 (sup. 2013), (in Japanese).
16.
Katsuyama
,
J.
,
Katsumata
,
G.
,
Onizawa
,
K.
,
Osakabe
,
K.
, and
Yoshimoto
,
K.
, 2015, “
Development of Probabilistic Evaluation Models of Fracture Toughness KIc and KIa for Japanese RPV Steels
,”
ASME
Paper No. PVP2015-45915.
You do not currently have access to this content.