Published May 2011
| Version v1
Miscellaneous
A Validation of CUPID Code for a Subcooled Boiling Test
- 1. Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)
Description
The Korea Atomic Energy Research Institute has been developing a three-dimensional thermal-hydraulic code, called CUPID, which was motivated from practical needs for the realistic simulation of two-phase flows in nuclear reactor components. This paper presents the implementation of the subcooled boiling model into the CUPID code and some assessment results. The closure relations for the subcooled boiling model are turbulence model, interfacial non-drag force, interfacial condensation, wall evaporation model, bubble departure diameter, and so on
Additional details
Publishing Information
- Publisher
- KNS
- Imprint Place
- Daejeon (Korea, Republic of)
- Imprint Title
- Proceedings of the KNS spring meeting
- Imprint Pagination
- [1 CD-ROM]
- Journal Page Range
- [2 p.]
Conference
- Title
- 2011 spring meeting of the KNS
- Dates
- 26-27 May 2011
- Place
- Taebaek (Korea, Republic of)
INIS
- Country of Publication
- Korea, Republic of
- Country of Input or Organization
- Korea, Republic of
- INIS RN
- 42099225
- Subject category
- S42: ENGINEERING; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- BUBBLES; C CODES; SUBCOOLED BOILING; THERMAL HYDRAULICS; TURBULENCE; TWO-PHASE FLOW; VALIDATION
- Descriptors DEC
- BOILING; COMPUTER CODES; FLUID FLOW; FLUID MECHANICS; HYDRAULICS; MECHANICS; PHASE TRANSFORMATIONS; TESTING
Optional Information
- Notes
- 6 refs, 4 figs, 1 tab