Published March 2012 | Version v1
Miscellaneous

Design and construction of the sodium thermal-hydraulic experimental facility: Stella-1

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

Description

A large-scale sodium thermal-hydraulic test program called STELLA (Sodium Test Loop for Safety Simulation and Assessment) and its first test facility aiming at a performance demonstration of the major components and the V and V of their design were briefly introduced with the preliminary CFD analysis results for assessing the thermal-hydraulic performance of the major heat exchangers, e. g. DHX (sodium-to-sodium decay heat exchanger) and AHX (sodium-to-air heat exchanger. High temperature design and analysis of each test heat exchanger have been carried out, and the features of creep-fatigue damage at critical parts of each test heat exchanger unit are also evaluated and discussed according to the high temperature design codes, e. g., ASME-NH and RCC-MR

Part of:
Proceedings of the 18th Pacific Basin Nuclear Conference

Additional details

Publishing Information

Publisher
Pacific Nuclear Council
Imprint Place
La Grange Park (United States)
Imprint Title
Proceedings of the 18th Pacific Basin Nuclear Conference
Imprint Pagination
[1 CD-ROM]
Journal Page Range
[10 p.]

Conference

Title
18. Pacific Basin Nuclear Conference
Acronym
PBNC 2012
Dates
18-23 Mar 2012
Place
Busan (Korea, Republic of)

INIS

Country of Publication
United States
Country of Input or Organization
Korea, Republic of
INIS RN
45032682
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference, Non-conventional Literature
Descriptors DEI
CREEP; DESIGN; FATIGUE; HEAT EXCHANGERS; PERFORMANCE; S CODES; TEST FACILITIES; THERMAL HYDRAULICS
Descriptors DEC
COMPUTER CODES; FLUID MECHANICS; HYDRAULICS; MECHANICAL PROPERTIES; MECHANICS

Optional Information

Notes
9 refs, 8 figs, 4 tabs