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ASTM Selected Technical Papers
Constraint Effects in Fracture
By
EM Hackett
EM Hackett
1
U.S. Nuclear Regulatory Commission
,
Washington, DC
;
symposium chairman and co-editor
Search for other works by this author on:
K-H Schwalbe
K-H Schwalbe
2
GKSS Research Center
,
Federal Republic of Germany
;
symposium co-chairman and co-editor
Search for other works by this author on:
RH Dodds, Jr Jr
RH Dodds, Jr Jr
3
University of Illinois
,
Urbana, IL
;
symposium co-chairman and co-editor
Search for other works by this author on:
ISBN-10:
0-8031-1481-8
ISBN:
978-0-8031-1481-4
No. of Pages:
514
Publisher:
ASTM International
Publication date:
1993

To help predict the behavior of a nuclear pressure vessel undergoing pressurized thermal shock, values of the arrest toughness are required. The purpose of the work described here is to show how toughness values can be calculated from the thickness reduction (TR) of the tested specimens and then used as “lower-bound” estimates. In the NIST wide-plate crack-arrest test program, 16 single edge-notched tension specimens were fractured, using the 26.7 MN universal testing machine. The first series of tests used HSST A533 Grade B Class 1 quenched and tempered steel, while the second series used a low upper-shelf 21/4 Cr-1 Mo steel. For each specimen the TR was measured on the two halves of the broken specimen and a contour map was constructed. The thickness reduction, TR, along the crack propagation plane can be related to the toughness, K, by the relationship K2 = E ∙ σY ∙ TR, where E is Young's modulus and σY an estimate of the tension effective yield strength adjusted for temperature, strain-rate, and constraint. The results show good agreement with values of K for arrest and reinitiation computed from a finite-element generation-mode analysis. Therefore, the indication of plastic work rate provided by the thickness reduction near the fracture plane is a useful preliminary assessment of the fracture toughness.

1.
Letter from G. R. Irwin to W. G. Reuter, INEL, Idaho Falls, Idaho, 31 Aug. 1989.
2.
Krafft
,
J. M.
and
Irwin
,
G. R.
, “
Crack-Velocity Considerations
,”
Fracture Toughness Testing and Its Applications
, STP 381,
American Society for Testing and Materials
,
Philadelphia
,
1965
, pp. 114–129.
3.
Naus
,
D. J.
,
Bass
,
B. R.
,
Pugh
,
C. E.
,
Nanstad
,
R. K.
,
Merkle
,
J. G.
,
Corwin
,
W. R.
, and
Robinson
,
G. C.
, “
Crack-Arrest Behavior in SEN Wide Plates of Quenched and Tempered A 533 Grade B Steel Tested Under Nonisothermal Conditions
,” NUREG/CR-4930 (ORNL-6388),
Oak Ridge National Laboratory
, prepared for the U.S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, Washington, DC (
08
1987
).
4.
Naus
,
D. J.
,
Keeney-Walker
,
J.
,
Bass
,
B. R.
,
Bolt
,
S. E.
,
Fields
,
R. J.
,
deWit
,
R.
, and
Low
,
S. R.
 III
, “
High-Temperature Crack-Arrest Behavior in 152-mm-Thick SEN Wide Plates of Quenched and Tempered A 533 Grade B Class 1 Steel
,” NUREG/CR-5330 (ORNL/TM-11083),
Oak Ridge National Laboratory and National Institute of Standards and Technology
, prepared for the U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research, Washington, DC 20555 (
04
1989
).
5.
Naus
,
D. J.
,
Keeney-Walker
,
J.
,
Bass
,
B. R.
,
Iskander
,
S. K.
,
Fields
,
R. J.
,
deWit
,
R.
, and
Low
,
S. R.
 III
, “
SEN Wide-Plate Crack-Arrest Tests Using A 533 Grade B Class 1 Material: WP-CE Test Series
,” NUREG/CR-5408 (ORNL/TM-11269),
Oak Ridge National Laboratory and National Institute of Standards and Technology
, prepared for the
U.S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research
, Washington, DC 20555 (
11
1989
).
6.
Naus
,
D. J.
,
Keeney-Walker
,
J.
,
Bass
,
B. R.
,
Robinson
,
G. C.
,
Iskander
,
S. K.
,
Fields
,
R. J.
,
deWit
,
R.
,
Low
,
S. R.
 III
,
Schwartz
,
C. W.
,
Alexander
,
D. J.
, and
Johansson
,
I.-B.
, “
Crack-Arrest Behavior in SEN Wide Plates of Low-Upper-Shelf Base Metal Tested Under Nonisothermal Conditions: WP-2 Series
,” NUREG/CR-5451 (ORNL/TM-6584),
Oak Ridge National Laboratory, National Institute of Standards and Technology, University of Maryland Department of Mechanical Engineering, and Swedish Royal Institute of Technology
, prepared for
the U.S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research
, Washington, DC 20555 (
08
1990
).
7.
Naus
,
D. J.
,
Keeney-Walker
,
J.
,
Bass
,
B. R.
,
Iskander
,
S. K.
,
Fields
,
R. J.
,
deWit
,
R.
, and
Low
,
S. R.
 III
, “
High-Temperature Crack-Arrest Tests Using 152-mm-Thick SEN Wide Plates of Low-Upper-Shelf Base Material: Tests WP-2.2 and WP-2.6
,” NUREG/CR-5450 (ORNL/TM-11352),
Oak Ridge National Laboratory and National Institute of Standards and Technology
, prepared for
the U.S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research
, Washington, DC 20555 (
02
1990
).
8.
Pugh
,
C. E.
,
Naus
,
D. J.
,
Bass
,
B. R.
,
Nanstad
,
R. K.
,
deWit
,
R.
,
Fields
,
R. J.
, and
Low
,
S. R.
 III
, “
Wide-plate Crack-Arrest Tests Utilizing a Prototypical Pressure Vessel Steel
,”
International Journal of Pressure Vessel and Piping
 0308-0161, Vol.
31
,
1988
, pp. 165–185.
9.
Naus
,
D. J.
,
Keeney-Walker
,
J.
,
Bass
,
B. R.
2
,
Fields
,
R. J.
,
deWit
,
R.
, and
Low
,
S. R.
 III
, “
High-Temperature Crack-Arrest Behavior of Prototypical and DeGraded (Simulated) Reactor Pressure Vessel Steels
,”
International Journal of Pressure Vessel and Piping
 0308-0161, Vol.
39
,
1989
, pp. 189–208.
10.
Naus
,
D. J.
,
Bass
,
B. R.
,
Keeney-Walker
,
J.
,
Fields
,
R. J.
,
deWit
,
R.
, and
Low
,
S. R.
 III
, “
HSST Wide-Plate Test Results and Analysis
,”
Nuclear Engineering and Design
 0029-5493, Vol.
119
,
1990
, pp. 283–295.
11.
ASME Boiler and Pressure Vessel Code, Section XI, “
Rules for Inservice Inspection of Nuclear Power Plant Components
,”
The American Society of Mechanical Engineers, United Engineering Center
,
New York, NY
.
12.
Crosley
,
P. B.
,
Fourney
,
W. L.
,
Hahn
,
G. T.
,
Hoagland
,
R. G.
,
Irwin
,
G. R.
, and
Ripling
,
E. J.
, “
Final Report on Cooperative Test Program on Crack Arrest Toughness Measurements
,” NUREG/CR-3261,
University of Maryland
, College Park, MD, prepared for
the U.S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research
, Washington, DC 20555 (
04
1983
).
13.
Barker
,
D. B.
,
Chona
,
R.
,
Fourney
,
W. L.
, and
Irwin
,
G. R.
, “
A Report on the Round Robin Program Conducted to Evaluate the Proposed ASTM Test Method for Determining the Crack Arrest Fracture Toughness, KIa, of Ferritic Materials
,” NUREG/CR-4996 (ORNL/Sub/79-7778/4),
University of Maryland
, College Park, MD, prepared for
the U.S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research
, Washington, DC 20555 (
01
1988
).
14.
ASTM Designation: E 1221-88, “
Standard Method for Determining Plane-Strain Crack-Arrest Fracture Toughness, KIa, of Ferritic Steels
,”
Annual Book of ASTM Standards, Section 3: Metals Test Methods and Analytical Procedures, Vol. 03.01, Metals-Mechanical Testing; Elevated and Low-Temperature Tests; Metallography
,
American Society for Testing and Materials
,
Philadelphia
.
15.
Cheverton
,
R. D.
and
Ball
,
D. G.
, “
The Role of Crack Arrest in the Evaluation of PWR Pressure Vessel Integrity during PTS Transients
,”
Engineering Fracture Mechanics
, Vol.
23
,
1986
, pp. 71–80.
16.
Bryan
,
R. H.
,
Bass
,
B. R.
,
Bolt
,
S. E.
,
Bryson
,
J. W.
,
Edmonds
,
D. P.
,
McCullough
,
R. W.
,
Merkle
,
J. G.
,
Nanstad
,
R. K.
,
Robinson
,
G. C.
,
Thomas
,
K. R.
, and
Whitman
,
G. D.
, “
Pressurized-Thermal-Shock Test of 6-in.-Thick Pressure Vessels. PTSE-1: Investigation of Warm Prestressing and Upper-Shelf Arrest
,” NUREG/CR-4106 (ORNL-6135),
Oak Ridge National Laboratory
, prepared for
the U.S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research
, Washington, DC.,
04
1985
.
17.
Bryan
,
R. H.
,
Bass
,
B. R.
,
Bolt
,
S. E.
,
Bryson
,
J. W.
,
Corwin
,
W. R.
,
Merkle
,
J. G.
,
Nanstad
,
R. K.
, and
Robinson
,
G. C.
, “
Pressurized-Thermal-Shock Test of 6-in.-Thick Pressure Vessels. PTSE-2: Investigation of Low Tearing Resistance and Warm Prestressing
,” NUREG/CR-4888 (ORNL-6377),
Oak Ridge National Laboratory
, prepared for
the U.S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research
, Washington, DC.,
12
1987
.
18.
Tada
,
H.
,
Paris
,
P. C.
, and
Irwin
,
G. R.
,
The Stress Analvsis of Cracks Handbook
,
Paris Productions, Inc.
,
St. Louis
,
1985
, pp. 2.10–2.15.
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