Analytical investigation and design of a model hydrodynamically simulating a prototype PWR core
Creators
Description
In order to ensure that data from vessel model flow tests are reliable, it is necessary to simulate hydrodynamically the various reactor components within the vessel, including the core. Modeling of the core is complex because, unlike other internals, a three-dimensional flow distribution must be taken into account. Core simulation criteria have been derived from the basic conservation laws governing fluid motion within the rod bundles that constitute the core. Using the criteria derived, along with any constraints imposed by the test loop, methodology for the design of a model core which hydrodynamically simulates the prototype core to a good degree of accuracy has been developed. Economic and fabrication considerations are taken into account in selecting the final design.
Additional details
Identifiers
- DOI
- 10.13182/nt72-a31217;
Publishing Information
- Journal Title
- Nuclear Technology
- Journal Volume
- 16
- Journal Issue
- 3
- Series
- Nucl. Technol.
- Journal Page Range
- 479-496
- ISSN
- 0029-5450
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 4059230
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- ANALYTICAL SOLUTION; FLUID FLOW; HEAT TRANSFER; HYDRODYNAMICS; MOCKUP; PWR TYPE REACTORS; REACTOR CORES
- Descriptors DEC
- FLUID MECHANICS; MECHANICS; REACTOR COMPONENTS; REACTORS; STRUCTURAL MODELS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- Updated automatically by Metadata and Full-Text Enrichment Agent