Published October 2017 | Version v1
Miscellaneous

APR1400 SG Support Stress Evaluation According to ASME BPVC Section III subsection NB and NF

  • 1. KEPCO International Nuclear Graduate School, Busan (Korea, Republic of)

Description

The integrity of SG support is important to prevent breach of pressure boundary that may results in release of radioactive coolant to the environment. Hence rigorous stress analysis is required to ensure intactness of structure for all operating condition. The SG support is welded into the primary head, hence the analysis model include support as well as part of primary head. The 2D axisymmetric model was created using ANSYS V.18.1 and analyzed for membrane and bending stress using linearized stress analysis post-process option. The resulting stresses for design and level A condition are within the allowable limits of ASME Section III, subsection NB and NF. In this study, the shell-type support system was re-evaluated in term of stress analysis. The stress condition in support shows that the current support can satisfy the requirements. A design for steam generator support had evaluated and analyzed by FEA method using ANSYS Workbench. The static structural analysis was conducted for some cases in some different positions. The analysis result was compared with ASME code limits to show that it follows the requirements. The report has verified the support's stress.

Part of:
Proceedings of the KNS 2017 Fall Meeting

Additional details

Publishing Information

Publisher
KNS
Imprint Place
Daejeon (Korea, Republic of)
Imprint Title
Proceedings of the KNS 2017 Fall Meeting
Imprint Pagination
[1 CD-ROM]
Journal Page Range
[4 p.]

Conference

Title
2017 Fall Meeting of the KNS
Dates
25-27 Oct 2017
Place
Kyungju (Korea, Republic of)

INIS

Country of Publication
Korea, Republic of
Country of Input or Organization
Korea, Republic of
INIS RN
49078816
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference, Non-conventional Literature
Descriptors DEI
A CODES; DESIGN; MAINTENANCE; PWR TYPE REACTORS; REACTOR COOLING SYSTEMS; RECOMMENDATIONS; STEAM GENERATORS; STRESS ANALYSIS; STRESSES; TOPOLOGY
Descriptors DEC
BOILERS; COMPUTER CODES; COOLING SYSTEMS; ENERGY SYSTEMS; ENRICHED URANIUM REACTORS; MATHEMATICS; POWER REACTORS; REACTOR COMPONENTS; REACTORS; THERMAL REACTORS; VAPOR GENERATORS; WATER COOLED REACTORS; WATER MODERATED REACTORS

Optional Information

Notes
3 refs, 11 figs, 6 tabs