Published May 2012
| Version v1
Miscellaneous
Determination of the Pipe Diameter and Length of a Sodium Experimental Installation for Single Phase Natural Convection Simulations
Creators
- 1. Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)
Description
As a part of the verification of PDRC(Passive Decay heat Removal Circuit) concept of DSFR(Demonstration Sodium-cooled Fast Reactor), KAERI will design and construct a large-scale sodium integral effect test facility called STELLA. This paper describes the selection method of the pipe of the experimental model installation, which should be designed so as to simulate various thermal-hydraulic features including the transient with natural convection heat transfer in the prototype. The scaling ratio of the model is one-fifth of the length scale, and the ratio of the temperature rise(ΔToR ) through the heat exchanger is the same with the same coolant as of the prototype
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
- 2012 spring meeting of the KNS
- Dates
- 16-18 May 2012
- Place
- Jeju (Korea, Republic of)
INIS
- Country of Publication
- Korea, Republic of
- Country of Input or Organization
- Korea, Republic of
- INIS RN
- 43073291
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- AFTER-HEAT REMOVAL; COMPUTERIZED SIMULATION; DESIGN; HEAT EXCHANGERS; NATURAL CONVECTION; PIPES; S CODES; SODIUM COOLED REACTORS; TEST FACILITIES; THERMAL HYDRAULICS; VERIFICATION
- Descriptors DEC
- COMPUTER CODES; CONVECTION; ENERGY TRANSFER; FLUID MECHANICS; HEAT TRANSFER; HYDRAULICS; LIQUID METAL COOLED REACTORS; MASS TRANSFER; MECHANICS; REACTORS; REMOVAL; SIMULATION; TUBES
Optional Information
- Notes
- 4 refs, 1 fig, 1 tab