Published October 2010
| Version v1
Miscellaneous
Preliminary Experiment of a Water Scaled Model for the Thermal Hydraulic Study of 600MWe-SFR
Creators
- 1. Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)
Description
KAERI has been developing a pool-type Sodiumcooled Fast Reactor (SFR). For a SFR development, one of the main topics is an enhancement of the reactor system safety. Thus, the large sodium experiments are planned to evaluate the reactor safety and component performance. Before a large sodium test, a scaled water model test had better be conducted due to several benefits. In this study, the thermal hydraulic behavior is investigated with a transparent 1/10 scaled reactor vessel model for the KALIMER-600 reactor. The scaled transparent water model facility is preliminarily operated at around 30 .deg. C water condition to check an operability of the experimental facility
Additional details
Publishing Information
- Publisher
- KNS
- Imprint Place
- Daejeon (Korea, Republic of)
- Imprint Title
- Proceedings of the KNS autumn meeting
- Imprint Pagination
- [1 CD-ROM]
- Journal Page Range
- [2 p.]
Conference
- Title
- 2010 autumn meeting of the KNS
- Dates
- 21-22 Oct 2010
- Place
- Jeju (Korea, Republic of)
INIS
- Country of Publication
- Korea, Republic of
- Country of Input or Organization
- Korea, Republic of
- INIS RN
- 42084918
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- PERFORMANCE; REACTOR EXPERIMENTAL FACILITIES; REACTOR VESSELS; SAFETY; SODIUM COOLED REACTORS; THERMAL HYDRAULICS
- Descriptors DEC
- CONTAINERS; FLUID MECHANICS; HYDRAULICS; LIQUID METAL COOLED REACTORS; MECHANICS; REACTOR COMPONENTS; REACTORS
Optional Information
- Notes
- 2 refs, 5 figs, 1 tab