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
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