Structural investigation of fuel rods basing on dynamic model of heat flow phenomena in fuel assemblies
- 1. Politechnika Poznanska, Pozunan (Poland)
Description
The structural investigation of reactor materials are usually by calculations determining the working conditions of particulars elements of fuel assemblies or the hole reactor core. For this analysis the mathematical model of heat flow phenomena was proposed which enable the calculations of temperature field within the assembly. The differential equations for mass, energy and momentum of cooling medium conservation in coaxial and transversal flow direction enable the steady state and transient analysis for the cases of change in heat flow in cooling medium velocity and the pressure in the assembly. The introduced empire correlation which are completing the set of equations make possible the analysis for violent changes of cladding temperature of fuel elements for cooling medium in two-phase flow. The computer program basing on the presented model was prepared for the calculations of initial parameters necessary for beginning the cladding and fuel material structural investigations. (author)
Additional details
Publishing Information
- Publisher
- Atomic Energy Society of Japan.
- Imprint Place
- Tokyo (Japan)
- Imprint Title
- Transactions of the 11th international conference on structural mechanics in reactor technology
- Imprint Pagination
- 6297 p.
- Journal Page Range
- v. C-D p. 91-96.
Conference
- Title
- 11. international conference on structural mechanics in reactor technology.
- Dates
- 18-23 Aug 1991.
- Place
- Tokyo (Japan).
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 23032007
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- FLOW MODELS; FUEL ASSEMBLIES; FUEL CANS; FUEL RODS; HEAT FLUX; NUMERICAL SOLUTION; STEADY-STATE CONDITIONS; TEMPERATURE DISTRIBUTION; TRANSIENTS; TWO-PHASE FLOW; WWER-5 REACTOR
- Descriptors DEC
- ENRICHED URANIUM REACTORS; FLUID FLOW; FUEL ELEMENTS; MATHEMATICAL MODELS; POWER REACTORS; PWR TYPE REACTORS; REACTOR COMPONENTS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS; WWER TYPE REACTORS
Optional Information
- Notes
- Imprint:Distributed by Maruzen Co. Ltd. P.O. Box 5050, Tokyo Int'l, 100-31 Japan ISBN 4-89047-060-3 for 17 vols. bound in 15 (A through SD2).