Published 1983 | Version v1
Book

Thermal buckling anlaysis of an LMFBR overflow vessel

Creators

  • 1. Westinghouse Hanford Co., Richland, WA (USA)

Description

During a reactor scram, cold sodium flows into the hot overflow vessel. The effect on the vessel is a compressive thermal stress in a zone just above the sodium level. This condition must be sufficiently controlled to preclude thermal buckling. Also, under repeated scrams, the vessel should not suffer thermal stress low cycle fatigue. To evaluate the closeness to buckling and satisfaction of ASME Code limits, a combination of simple approximations, detailed elastic shell buckling analyses, and correlations to results of thermal buckling tests were employed. This paper describes the analysis methods, special considerations, and evaluations accomplished for this FFTF vessel to assure satisfaction of ASME buckling design criteria, rules, and limits. ASME Code Case N-47 (and its predecessor Case 1331) buckling limits, rules, and safety factors required some interpretation for this application. Analytical model difficulties that were overcome include accounting for nonsymmetrical strip thermal compressions, shell imperfection effects, and plasticity effects. An outcome of these analyses was the recognition that buckling of shells due to a narrow strip of compressive membrane strains occurs at a strain considerably higher than that of a uniformly compressed shell. The cause is the prebuckling deformation and ridging. (orig.)

Additional details

Publishing Information

Publisher
North-Holland.
Imprint Place
Amsterdam (Netherlands)
ISBN
0444 86694 9
Imprint Title
Transactions of the 7. international conference on structural mechanics in reactor technology. Vol. E
Imprint Pagination
751 p.
Journal Page Range
p. 133-140.

Conference

Title
7. international seminar on computational aspects of the finite element method (CAFEM-7) in conjunction with the 7. international conference on structural mechanics in reactor technology (SMIRT-7).
Dates
22-26 Aug 1983.
Place
Chicago, IL (USA).

INIS

Country of Publication
Netherlands
Country of Input or Organization
Netherlands
INIS RN
15050104
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
DEFORMATION; DYNAMIC LOADS; LMFBR TYPE REACTORS; REACTOR VESSELS; REGULATIONS; THERMAL STRESSES; TIME DEPENDENCE
Descriptors DEC
BREEDER REACTORS; CONTAINERS; EPITHERMAL REACTORS; FAST REACTORS; FBR TYPE REACTORS; LAW; LIQUID METAL COOLED REACTORS; REACTORS; STRESSES

Optional Information

Notes
Imprint:Vol. D and E bound in one volume.
Secondary number(s)
EUR--8596 DE/EN/FR.