Published 2000 | Version v1
Miscellaneous

Stress analysis of steam generator row-1 tubes

  • 1. KAERI, Taejon (Korea, Republic of)
  • 2. Chungbuk National Univ., Cheongju (Korea, Republic of)

Description

Residual stresses induced in U-bending and tube-to-tubesheet joining processes of PWR's steam generator row-1 tube were measured by X-ray method and Hole-Drilling Method(HDM). The stresses resulting from the internal pressure and the temperature gradient in the steam generator were also estimated theoretically. In U-bent regions, the residual stresses at extrados were induced with compressive stress(-), and its maximum value reached -319 Mpa in axial direction at ψ=0 .deg. in position. Maximum tensile residual stress of 170 MPa was found to be at the flank side at position of ψ=90 deg., i.e., at apex region. In tube-to-tubesheet joining methods, the residual stresses induced by the explosive joint method were found to be lower than that by the mechanical roll method. The gradient of residual stress along the expanded tube was highest at the transition region, and the residual stress in circumferential direction was found to be higher than the residual stress in axial direction. Hoop stress due to an internal pressure between primary and secondary side was analyzed to be 76 MPa and thermal stress was 45 MPa

Part of:
Proceedings of the KSME 2000 spring annual meeting A

Additional details

Publishing Information

Publisher
KSME
Imprint Place
Seoul (Korea, Republic of)
Imprint Title
Proceedings of the KSME 2000 spring annual meeting A
Imprint Pagination
928 p.
Journal Page Range
p. 25-30

Conference

Title
KSME 2000 spring annual meeting A
Dates
20-22 Apr 2000
Place
Ulsan (Korea, Republic of)

INIS

Country of Publication
Korea, Republic of
Country of Input or Organization
Korea, Republic of
INIS RN
36036246
Subject category
S36: MATERIALS SCIENCE;
Resource subtype / Literary indicator
Conference, Non-conventional Literature
Descriptors DEI
EXPANSION; PWR TYPE REACTORS; RESIDUAL STRESSES; STEAM GENERATORS; TEMPERATURE GRADIENTS; TENSILE PROPERTIES; THERMAL STRESSES; TUBES
Descriptors DEC
BOILERS; ENRICHED URANIUM REACTORS; MECHANICAL PROPERTIES; POWER REACTORS; REACTORS; STRESSES; THERMAL REACTORS; VAPOR GENERATORS; WATER COOLED REACTORS; WATER MODERATED REACTORS

Optional Information

Notes
9 refs, 9 figs, 2 tabs