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ASTM Selected Technical Papers
Probabilistic Fracture Mechanics and Fatigue Methods: Applications for Structural Design and Maintenance
By
JM Bloom
JM Bloom
1
Babcock & Wilcox, Research and Development Division Alliance
,
Ohio
;
symposium cochairman and editor
.
Search for other works by this author on:
JC Ekvall
JC Ekvall
2
Lockheed-California Company
,
Burbank, Calif.
;
symposium cochairman and editor
.
Search for other works by this author on:
ISBN-10:
0-8031-0242-9
ISBN:
978-0-8031-0242-2
No. of Pages:
223
Publisher:
ASTM International
Publication date:
1983

In this paper the results of a probabilistic analysis for a pressure vessel are described in which the effects of various conservatisms used in Section III, Appendix G, of the ASME Boiler and Pressure Vessel Code are assessed. The methodology used is based on the introduction of probabilistic concepts into the deterministic calculations of Section III, Appendix G, so that the appropriate variability is reflected. By comparing the estimated probabilities of failure based on the various conservatisims, the approximate margin of safety in the design of a pressure vessel has been evaluated. From this analysis, it is concluded that this safety margin is considerable. Depending upon the conditions considered to be realistic in practice, the margin could be upwards of 10 or more orders of magnitude.

1.
ASME Boiler and Pressure Vessel Code
, Section III, Appendix G, “
Protection Against Nonductile Failure
,”
American Society of Mechanical Engineers
,
New York
,
1974
, p. 487.
2.
United States Nuclear Regulatory Commission
, Regulatory Guide 1.99, “
Effects of Residual Elements on Predicted Radiation Damage to Reactor Vessel Materials
,” Revision 1,
04
1977
, pp. 1.99-3.
3.
Buchalet
,
C. B.
and
Bamford
,
W. H.
, “
Method For Fracture Mechanics Analysis of Nuclear Reactor Vessels under Severe Thermal Transients
,” Paper 75-WA/PVP-3,
Pressure Vessels and Piping Division, American Society of Mechanical Engineers
, Winter Meetings,
12
1975
.
4.
Jouris
,
G. M.
and
Shaffer
,
D. H.
, “
Probabilistic Brittle Fracture Analysis For Major Thermal Transients in Pressure Vessels
.”
Proceedings
,
3rd International Conference on Structural Reliability in Reactor Technology
, Paper G3/3
London
,
09
1975
.
5.
Hammersly
,
J. W.
and
Handscomb
,
D. C.
,
Monte Carlo Methods
,
Methuen & Co.
,
London
,
1964
.
6.
Nagel
,
P. M.
, “
Importance Sampling in Systems Simulation,
Fifth Annual Conference on ability and Maintainability
, 18–20 July 1966,
New York, N.Y.
7.
Pollyak
,
Yu G.
, “
Estimation of Small Probabilities in Statistical Simulation of Systems
,”
Engineering Cybernetics
,
1971
, pp. 342-349.
8.
Schroder
,
R. J.
, “
Fault Trees for Reliability Analysis
,”
Proceedings
,
1970 Annual Symposium on Reliability
, 3–5 Feb. 1970,
Los Angeles
, pp. 198-205.
9.
Spanier
,
J.
, “
An Analytic Approach to Variance Reduction
,”
SIAM Journal of Applied Mathematics
, Vol.
18
,
1970
, pp. 172-190.
10.
Spanier
,
J.
, “
A New Multi-Stage Procedure for Systematic Variance Reduction in Monte Carlo
,”
Proceedings
,
Conference on Reactor Mathematics and Applications
,
Idaho
, CONF-710302, Vol.
II
,
U.S. Atomic Energy Commission
,
1971
, pp. 760-770.
11.
Walsh
,
J. E.
, “
Questionable Usefulness of Variance for Measuring Estimate Accuracy in Monte Carlo Importance Sampling Problems
,”
Symposium on Monte Carlo Method
,
Meyer
H. A.
, Ed.,
Wiley
,
1956
, pp. 141-146.
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