Load and Resistance Factor Design (LRFD) of Nuclear Straight Pipes for Loads That Cause Primary Stress

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]  Bilal M. Ayyub,et al.  A Reliability-Based Approach for the Design of Nuclear Piping for Internal Pressure , 2009 .

[2]  Bilal M. Ayyub,et al.  Strength Model Uncertainties of Burst, Yielding, and Excessive Bending of Piping , 2009 .

[3]  Kleio Avrithi Reliability-Based Design Of Piping: Internal Pressure, Gravity, Earthquake, and Thermal Expansion , 2007 .

[4]  Rakesh Kumar Saigal Seismic Analysis and Reliability-based Design of Secondary Systems , 2005 .

[5]  Bilal M. Ayyub,et al.  Probability, Statistics, and Reliability for Engineers and Scientists , 2003 .

[6]  Bruce R. Ellingwood Event Combination Analysis for Design and Rehabilitation of U.S. Army Corps of Engineers Navigation Structures. , 1995 .

[7]  T. Sotberg,et al.  Reliability-based pipeline design and code calibration , 1994 .

[8]  Bruce R. Ellingwood,et al.  Probabilistic methods for condition assessment and life prediction of concrete structures in nuclear power plants , 1993 .

[9]  R. F. Reedy,et al.  Guidelines for piping system reconciliation (NCIG-05, Revision 1): Final report , 1988 .

[10]  Bruce R. Ellingwood,et al.  Probability‐Based Design Criteria for Nuclear Plant Structures , 1987 .

[11]  Lucia Faravelli,et al.  Load combination by partial safety factors , 1983 .

[12]  M. Reich,et al.  Probabilistic models for operational and accidental loads on seismic category I structures , 1983 .

[13]  E. C. Rodabaugh,et al.  Evaluation of the plastic characteristics of piping products in relation to ASME code criteria , 1978 .

[14]  W. F. Simmons,et al.  Report on The Elevated-Temperature Properties of Stainless Steels , 1952 .