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Title: Simplified inelastic analysis method based on r-factor.


No abstract prepared.

Publication Date:
Research Org.:
Argonne National Lab. (ANL), Argonne, IL (United States)
Sponsoring Org.:
OSTI Identifier:
Report Number(s):
TRN: US0805642
DOE Contract Number:
Resource Type:
Resource Relation:
Journal Name: Trans. Am. Nucl. Soc. Vol. 94; Journal Issue: 2006; Conference: 2006 ANS Annual Meeting; Jun 4-8, 2006; Reno, Nevada
Country of Publication:
United States

Citation Formats

Majumdar, S., and Energy Technology. Simplified inelastic analysis method based on r-factor.. United States: N. p., 2006. Web.
Majumdar, S., & Energy Technology. Simplified inelastic analysis method based on r-factor.. United States.
Majumdar, S., and Energy Technology. Sun . "Simplified inelastic analysis method based on r-factor.". United States. doi:.
title = {Simplified inelastic analysis method based on r-factor.},
author = {Majumdar, S. and Energy Technology},
abstractNote = {No abstract prepared.},
doi = {},
journal = {Trans. Am. Nucl. Soc. Vol. 94},
number = 2006,
volume = ,
place = {United States},
year = {Sun Jan 01 00:00:00 EST 2006},
month = {Sun Jan 01 00:00:00 EST 2006}

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  • A new semi-empirical method, based on the use of the P-factor (P = N/sub p/N/sub n//(N/sub p/+N/sub n/)), is shown to simplify significantly the systematics of atomic masses. Its uses is illustrated for actinide nuclei where complicated patterns of mass systematics seen in traditional plots versus Z, N, or isospin are consolidated and transformed into linear ones extending over long isotopic and isotonic sequences. The linearization of the systematics by this procedure provides a simple basis for mass prediction. For many unmeasured nuclei beyond the known mass surface, the P-factor method operates by interpolation among data for known nuclei rathermore » than by extrapolation, as is common in other mass models.« less
  • This paper presents two simplified methods which are capable of analyzing complex piping systems under elevated temperature. Both methods employ beam-type elements based on the force method and take account of interactive effects of combined moments. One of the methods consists of two steps of calculation; deformation of piping systems are first analyzed in the elastic-creep range, and secondly stress and strain of the single bend of interest are calculated by stress analysis program. The other is applicable to the problems in the elastic-plastic-creep range. The common constitutive relations of material nonlinealities are employed to derive an equilibrium equation ofmore » an element, in which plastic deformations are treated as a special case of creep one. The MARC program as well as the two simplified methods are applied to the three typical problems of piping systems. As a first example, a piping system with four elbows is analyzed in order to verify the validity of the simplified methods. Secondly, under actual loading and boundary conditions, a complicated piping system is analyzed by the simplified methods. Finally, the problem of three anchor piping system subjected to thermal expansion will also be calculated to investigate redistribution of plastic strains in the system.« less
  • It is generally recognized that contemporary inelastic analysis of elevated temperature equipment designed to Section III of the ASME Code can be extremely complex, time consuming, and expensive. The major obstacle to simplifications of the inelastic analysis is the concern that strain redistribution mechanisms will be missed in the simplifications. However, when it can be shown that these mechanisms are not significant, considerable simplifications of inelastic models can be justified and accomplished. Further simplifications may be justified when the consideration of inelastic behavior is limited to a specific design application, material, and service condition. Alloy 2-1/4 Cr 1 Mo, primarilymore » because of its low creep rupture strength and a relatively high yield stress at temperatures between 800/sup 0/F (427/sup 0/C) and 1000/sup 0/F (538/sup 0/C), is greatly limited in its inelastic response by the Code creep-fatigue allowables. This limitation, although undesirable from the low limit it places on allowable stresses, can be used to advantage in justifying simplifications in inelastic analysis for design evaluation. This paper presents a simplified procedure and justification for its use for creep-fatigue and ratchetting evaluation of 2-1/4 Cr 1- Mo steam generators operating between 800/sup 0/F (427/sup 0/C) and 1000/sup 0/F (538/sup 0/C).« less
  • Screening rules and preliminary design of FFTF piping were developed in 1974 based on expected behavior and engineering judgment, approximate calculations, and a few detailed inelastic analyses of pipelines. This paper provides findings from six additional detailed inelastic analyses with correlations to the simplified analysis screening rules. In addition, simplified analysis methods for treating weldment local stresses and strains as well as fabrication induced flaws are described. Based on the FFTF experience, recommendations for future Code and technology work to reduce design analysis costs are identified.