Published July 1973
| Version v1
Journal article
Thermal analysis of the Pennsylvania State University Breazeale nuclear reactor
Creators
Description
An experimental and analytical program has been performed to study the temperature distribution, as a function of reactor power, in the TRIGA reactor at The Pennsylvania State University. A two-dimensional digital computer program written in FORTRAN language numerically solves Poisson's heat equation using finite difference techniques.Experimental measurements of the fuel temperature in the core midplane and in the water over a large portion of the core are incorporated into the computer code, which permits determining the temperature distribution through the core as a function of power. Several interesting results were obtained, one of which showed that sub cooled boiling commences in the core between 150 and 200 kW.
Additional details
Identifiers
- DOI
- 10.13182/nt73-a31313;
Publishing Information
- Journal Title
- Nuclear Technology
- Journal Volume
- 19
- Journal Issue
- 1
- Series
- Nucl. Technol.
- Journal Page Range
- 6-15
- ISSN
- 0029-5450
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 4086008
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- COMPUTER CALCULATIONS; COMPUTER CODES; FINITE DIFFERENCE METHOD; POISSON EQUATION; PSTR REACTOR; REACTOR CORES; SUBCOOLED BOILING; TEMPERATURE DEPENDENCE; THERMAL ANALYSIS; TRIGA TYPE REACTORS; WATER
- Descriptors DEC
- BOILING; DIFFERENTIAL EQUATIONS; ENRICHED URANIUM REACTORS; EQUATIONS; HOMOGENEOUS REACTORS; HYDRIDE MODERATED REACTORS; ITERATIVE METHODS; NUMERICAL SOLUTION; PHASE TRANSFORMATIONS; POOL TYPE REACTORS; REACTOR COMPONENTS; REACTORS; RESEARCH AND TEST REACTORS; RESEARCH REACTORS; SOLID HOMOGENEOUS REACTORS; THERMAL REACTORS; TRAINING REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- Updated automatically by Metadata and Full-Text Enrichment Agent