Research program: the investigation of heat transfer and fluid flow at low pressure
Description
This paper gives an overview of a multiyear joint research program being conducted at the University of New Mexico (UNM) with support from Sandia National Laboratories and GA Technologies. This research focuses on heat removal and fluid dynamics in flow regimes characterized by low pressure and low Reynolds number. The program was motivated by a desire to characterize and analyze cooling in a broad class of TRIGA-type reactors under: (a) typical operating conditions, (b) anticipated, new operating regimes, and (c) postulated accident conditions. It has also provided experimental verification of analytical tools used in design analysis. The paper includes descriptions of the UNM thermal-hydraulics test facility and the experimental test sections. During the first two years experiments were conducted using single, electrically heated rod in water and air annuli. This configuration provides an observable and serviceable simulation of a fuel rod and its coolant channel
Availability note (English)
MF available from INIS under the Report Number; Available from NTIS, PC A02/MF A01; 1 as DE86009379.
Files
Additional details
Publishing Information
- Imprint Pagination
- 20 p.
- Report number
- SAND--86-0255C
Conference
- Title
- 10. U.S. TRIGA user's conference.
- Dates
- 7-9 Apr 1986.
- Place
- College Station, TX (USA).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 17078886
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- ANNULAR FUEL ELEMENTS; CRITICAL HEAT FLUX; FLUID FLOW; FUEL RODS; HEAT TRANSFER; HYDRAULICS; LAMINAR FLOW; LOSS OF COOLANT; NATURAL CONVECTION; NUSSELT NUMBER; REYNOLDS NUMBER; TRIGA TYPE REACTORS
- Descriptors DEC
- ACCIDENTS; CONVECTION; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; FUEL ELEMENTS; HEAT FLUX; HOMOGENEOUS REACTORS; HYDRIDE MODERATED REACTORS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTORS; RESEARCH AND TEST REACTORS; SOLID HOMOGENEOUS REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- Portions of this document are illegible in microfiche products.
- Secondary number(s)
- CONF-8604117--3.