Published May 2017 | Version v1
Miscellaneous

Stress analysis of IHX Facility in SFR

  • 1. Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

Description

The intermediate heat exchangers which are located at the boundary of the hot and cold pools (classification of Redan), strongly influence the heat transportation from the primary side to the secondary side through the piping line situated at the internal flow path. Therefore, investigation of IHX is of importance for the design of the SFR concept. The IHX performances were tested in Intermediate Heat Exchanger test Loop for PGSFR Safety (IHELPS) experimental facility of KAERI. However, instead of sodium, water was selected as the working fluid. The purpose The IHX facility has several duct. And duct is a rectangular shape. For shape preservation, it should be neither transformed nor damaged in an actual test. Therefore, SolidWorks Simulation based structural analysis was conducted for securing the integrity of IHX facility. The performance of intermediate heat exchanger were tested in IHELPS experimental facility. The characteristics of the prototype IXH in the SFR design concept were preserved in IHELPS experiments followed the scale-down rules. By using the SolidWorks Simulation program, the stress on inner duct of IHX were analyzed. The analytical results showed satisfactory performance of the scale-downed IHX in comparison of ASME VIII Div.1 criterion. The CFD calculation results showed that the integrity of the IHX were preserved under static and dynamic state conditions.

Part of:
Proceedings of the KNS 2017 Spring Meeting

Additional details

Publishing Information

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

Conference

Title
2017 Spring Meeting of the KNS
Dates
17-19 May 2017
Place
Jeju (Korea, Republic of)

INIS

Country of Publication
Korea, Republic of
Country of Input or Organization
Korea, Republic of
INIS RN
49050344
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference, Non-conventional Literature
Descriptors DEI
COMPUTER CALCULATIONS; DESIGN; HEAT EXCHANGERS; PERFORMANCE; SAFETY; SODIUM COOLED REACTORS; STRESS ANALYSIS
Descriptors DEC
LIQUID METAL COOLED REACTORS; REACTORS

Optional Information

Notes
3 refs, 3 figs