Background for Changes in the 1981 Edition of the ASME Nuclear Power Plant Components Code for Controlling Primary Loads in Piping Systems

S. E. Moore; E. C. Rodabaugh

doi:10.1115/1.3264228

Journal of Pressure Vessel Technology | Volume 104 | Issue 4 | PRESSURE VESSEL AND PIPING CODES

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PRESSURE VESSEL AND PIPING CODES

Background for Changes in the 1981 Edition of the ASME Nuclear Power Plant Components Code for Controlling Primary Loads in Piping Systems

S. E. Moore and E. C. Rodabaugh

[+] Author and Article Information

S. E. Moore

Oak Ridge National Laboratory, Oak Ridge, Tenn. 37830

E. C. Rodabaugh

E. C. Rodabaugh Associates, Hilliard, Ohio 43026

J. Pressure Vessel Technol 104(4), 351-361 (Nov 01, 1982) (11 pages) doi:10.1115/1.3264228 History: Received August 25, 1981; Revised July 30, 1982; Online November 05, 2009

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Abstract

Section III of the ASME Boiler and Pressure Vessel Code contains simplified design formulas for placing bounds on the plastic deformations in nuclear power plant piping systems. For Class 1 piping a simple equation is given in terms of primary load stress indices (B 1 and B 2 ) and nominal pressure and bending stresses. The B 1 and B 2 stress indices reflect the capacities of various piping products to carry load without gross plastic deformation. In this paper, the significance of the indices, nominal stresses, and limits given in the Code for Class 1 piping and corresponding requirements for Class 2 and Class 3 piping are discussed. Motivation behind recent (1978–1981) changes in the indices and in the associated stress limits is presented.

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Moore SE, Rodabaugh EC. Background for Changes in the 1981 Edition of the ASME Nuclear Power Plant Components Code for Controlling Primary Loads in Piping Systems. ASME. J. Pressure Vessel Technol. 1982;104(4):351-361. doi:10.1115/1.3264228.

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Background for Changes in the 1981 Edition of the ASME Nuclear Power Plant Components Code for Controlling Primary Loads in Piping Systems

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