Published March 1997 | Version v1
Report Open

Designing of fast reactor equipment and pipelines: Normative method for calculation of long-term cyclic strength

  • 1. OKBM, Nizhny Novgorod (Russian Federation)

Description

The paper deals with the method for calculational analysis of long-term cyclic strength recommended by ''Norms for strength...'' to estimate cyclic damage of equipment items being operated at temperatures which cause creep and loaded by repeated thermal or mechanical forces. The paper gives formulae interrelating amplitude of allowable conditional elastic stresses [σAF] and allowable number [N0] of cycles, as well as calculational fatigue curves for alloyed steels, corrosion-resistant austenitic steels at loading duration of 1·105 hours. The paper describes the method for calculational analysis of long-term cyclic strength for items made from steels with non-metallic inclusions, for items contacting with corrosion-aggressive media, welded joints etc. An example of calculational analysis of long-term cyclic strength by the use of recommended normative method is given. It is shown that the item analyzed as an example (the joint of upper tube sheet of BN-600 intermediate heat exchanger and outer shell) has cyclic strength meeting the requirements of ''Norms for strength...'' valid in Russia. (author). 2 refs, 6 figs, 14 tabs

Files

28042991.pdf

Files (305.0 kB)

Name Size Download all
md5:09d3078f1ca4754f7c84886eab284ba0
305.0 kB Preview Download
Part of:
Creep-fatigue damage rules for advanced fast reactor design. Proceedings of a technical committee meeting

Additional details

Publishing Information

Imprint Title
Creep-fatigue damage rules for advanced fast reactor design. Proceedings of a technical committee meeting
Imprint Pagination
282 p.
Journal Page Range
p. 31-46.
ISSN
1011-4289
Report number
IAEA-TECDOC--933

Conference

Title
Technical committee meeting on creep-fatigue damage rules for advanced fast reactor design.
Dates
11-13 Jun 1996.
Place
Manchester (United Kingdom).

INIS

Country of Publication
International Atomic Energy Agency (IAEA)
Country of Input or Organization
International Atomic Energy Agency (IAEA)
INIS RN
28042991
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
CALCULATION METHODS; CREEP; DESIGN; ELASTICITY; EQUIPMENT; FAILURES; FATIGUE; LMFBR TYPE REACTORS; PIPELINES; STEELS; STRAINS
Descriptors DEC
ALLOYS; BREEDER REACTORS; CARBON ADDITIONS; EPITHERMAL REACTORS; FAST REACTORS; FBR TYPE REACTORS; IRON ALLOYS; IRON BASE ALLOYS; LIQUID METAL COOLED REACTORS; MECHANICAL PROPERTIES; REACTORS; TRANSITION ELEMENT ALLOYS

Optional Information