Class 2 and 3 nuclear piping is designed according to the allowable stress design (ASD) method used in the ASME Boiler and Pressure Vessel (B&PV) code, Sec. III, Division 1, NC and ND-3600 according to which safety factors applied to the strength of steel (resistance) provide acceptable safety margins for the piping design. This paper describes the development of design equations according to the load and resistance factor design (LRFD) method for loads that cause primary stress such as sustained weight, internal pressure, and earthquake for different levels of piping operation. The LRFD method differs from the ASD since multiple factors, applied separately to each load and the strength of steel, provide safety margins that correspond to a known and acceptable probability of failure for the piping. Load combinations are provided, statistical properties for the variables under consideration are presented and the partial safety factors are moreover illustrated for different values of the target reliability index.

1.
American Society of Mechanical Engineers
, 2001, “
Rules for Construction of Nuclear Facility Components
,” Boiler and Pressure Vessel Code, ASME, New York.
2.
Ayyub
,
B. M.
,
Gupta
,
A.
,
Assakkaf
,
I.
,
Shah
,
N.
,
Kotwicki
,
P.
, and
Avrithi
,
K.
, 2007, “
Development of Reliability-Based Load and Resistance Factor Design (LRFD) Methods for Piping
,” ASME Research Task Force on the Development of Reliability-Based Load and Resistance Factor Design (LRFD) Methods for Piping, ASME Report No. CRDT-86.
3.
Mello
,
R. M.
, and
Griffin
,
D. S.
, 1974, “Plastic Collapse Loads for Pipe Elbows Using Inelastic Analysis,” ASME Paper No. 74-PVP-16.
4.
Rodabaugh
,
E. G.
, and
Moore
,
S. E.
, 1978, “
Evaluation of the Plastic Characteristics of Piping Products in Relation to ASME Code Criteria
,” Battelle-Columbus Laboratories, Columbus, OH.
5.
American Association of State Highway and Transportation Officials
, 1994, LRFD Bridge Design and Construction Specifications, AASHTO, Washington, DC.
6.
American Concrete Institute International
, 2001, “
Standard Code Requirements for Nuclear Safety Related Concrete Structures
,” ACI 349-01.
7.
American Concrete Institute
, 1977, “
Building Code Requirements for Reinforced Concrete
,” ACI 318-77, Detroit, MI.
8.
American Institute for Steel Construction
, 2003, “
Load and Resistance Factor Design Specification for Safety-Related Steel Structures for Nuclear Facilities
,” ANSI/AISC N690L-03.
9.
American Society of Civil Engineers
, 1992,
Load and Resistance Factor Design: Specification for Engineered Wood Construction
,
ASCE
,
New York
.
10.
Avrithi
,
K.
, 2007, “
Reliability-Based Design of Piping: Internal Pressure, Gravity, Earthquake, and Thermal Expansion
,” Ph.D. thesis, University of Maryland, College Park, MD.
11.
Avrithi
,
K.
, and
Ayyub
,
B. M.
, 2009 “
Strength Model Uncertainties of Burst and Excessive Bending of Piping
,”
ASME J. Pressure Vessel Technol.
0094-9930,
131
(
3
), p.
031207
.
12.
Simmons
,
W. F.
, and
Van Echo
,
J. A.
, 1965, “
Elevated-Temperature Properties of Stainless Steels
,” ASTM, DS 5-S1, Philadelphia, PA.
13.
Mikita
,
R. W.
, and
Reedy
,
R. F.
, 1988, “
Guidelines for Piping System Reconciliation (NCIG-05, Revision 1): Final Report
,” Report No. EPRI-NP-5639.
14.
Hwang
,
H.
,
Wang
,
P. C.
,
Shooman
,
M.
, and
Reich
,
M.
, 1983, “
A Consensus Estimation Study of Nuclear Power Plant Structural Loads
,” NUREG/CR-3315.
15.
Hwang
,
H.
,
Wang
,
P. C.
, and
Reich
,
M.
, 1983, “
Probabilistic Models for Operational and Accidental Loads on Seismic Category I Structures
,” NUREG/CR-3342.
16.
Avrithi
,
K.
, and
Ayyub
,
B. M.
, 2009, “
A Reliability-Based Approach for the Design of Nuclear Piping for Internal Pressure
,”
ASME J. Pressure Vessel Technol.
0094-9930,
131
(
4
), p.
041201
.
17.
Ayyub
,
B. M.
, and
McCuen
,
R. H.
, 2003,
Probability, Statistics and Reliability for Engineers and Scientists
,
CRC
,
Boca Raton, FL
.
18.
Bishop
,
B. A.
, and
Phillips
,
J. H.
, 1993, “
Prioritizing Aged Piping for Inspection Using a Simple Probabilistic Analysis Model
,”
PVP (Am. Soc. Mech. Eng.)
0277-027X,
251
, pp.
141
152
.
19.
Casciati
,
F.
, and
Faravelli
,
L.
, 1983, “
Load Combination by Partial Safety Factors
,”
Nucl. Eng. Des.
0029-5493,
75
, pp.
439
452
.
20.
Casciati
,
F.
, 1983, “
Partial Safety Factors for Combined Loading
,”
Transactions of the International Conference on Structural Mechanics in Reactor Technology
, pp.
57
64
.
21.
Ellingwood
,
B. R.
, 1995, “
Event Combination Analysis for Design and Rehabilitation of U. S. Army Corps of Engineers Navigation Structures
,” WES ITL-95-2, U.S. Army Corps of Engineers.
22.
Ellingwood
,
B. R.
, and
Yasuhiro
,
M.
, 1993, “
Probabilistic Methods for Condition Assessment and Life Prediction of Concrete Structures in Nuclear Power Plants
,”
Nucl. Eng. Des.
0029-5493,
142
, pp.
155
166
.
23.
Hwang
,
H.
,
Ellingwood
,
B.
,
Shinozuka
,
M.
, and
Reich
,
M.
, 1987, “
Probability-Based Design Criteria for Nuclear Plant Structures
,”
J. Struct. Eng.
0733-9445,
113
(
5
), pp.
925
942
.
24.
Saigal
,
R. K.
, 2005, “
Seismic Analysis and Reliability-Based Design of Secondary Systems
,” Ph.D. thesis, North Carolina State University, Raleigh, NC.
25.
Sotberg
,
T.
, and
Leira
,
B. J.
, 1994, “
Reliability-Based Pipeline Design and Code Calibration
,” OMAE Pipeline Technology, Vol.
V
, pp.
351
363
.
26.
Stancampiano
,
P. A.
, and
Zemanick
,
P. P.
, 1976, “
Estimates of the Burst Reliability of Thin-Walled Cylinders Designed to Meet the ASME Code Allowables
,”
International Joint Pressure Vessels and Piping and Petroleum Mechanical Engineering Conference
, Mexico City, Mexico.
27.
Stewart
,
G.
,
Klever
,
F. J.
, and
Ritchie
,
D.
, 1994, “
An Analytical Model to Predict the Burst Capacity of Pipelines
,” OMAE Pipeline Technology, Vol. V.
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