Interpretation of gamma-scanning data from the ORR demonstration elements

Conference · Sun Jan 01 00:00:00 EST 1989

OSTI ID:5381361

Bretscher, M M; Snelgrove, J L; Hobbs, R W ^[1]

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1. Argonne National Lab., IL (USA)

The HEU and LEU fuel elements used in the ORR whole-core demonstration were gamma-scanned to determine the axial distribution of the {sup 140}La and {sup 137}Cs activities. Analysis of this data is now complete. From the {sup 140}La activity distributions cycle-averaged powers were determined while the {sup 137}Cs data provided a measure of the final {sup 235}U burnup in the fuel elements. A method for calculating correction factors for activity gradients transverse to the fuel element axis is presented and is applied to the first mixed core used in the demonstration during the gradual transition to an all LEU core. Results based on the gamma-scanning of the LEU fuel followers are also presented. Improved burnup calculations against which the experimental results are to be compared are now in progress. 7 refs., 21 figs., 3 tabs.

• Research Organization: Argonne National Lab., IL (USA)
• Sponsoring Organization: ACDA; DOE/IE
• DOE Contract Number: W-31109-ENG-38
• OSTI ID: 5381361
• Report Number(s): CONF-8909141-8; ON: DE90001761; TRN: 89-032220
• Resource Relation: Conference: 12. international meeting on reduced enrichment for research and test reactors, Berlin (Germany, F.R.), 10-13 Sep 1989
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
99 GENERAL AND MISCELLANEOUS//MATHEMATICS, COMPUTING, AND INFORMATION SCIENCE
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
ORR REACTOR
FUEL ELEMENTS
BURNUP
CALIBRATION
CESIUM 137
COMPARATIVE EVALUATIONS
COMPUTERIZED SIMULATION
DATA ANALYSIS
DEMONSTRATION PROGRAMS
EXPERIMENTAL DATA
FISSION PRODUCTS
GAMMA FUEL SCANNING
HIGHLY ENRICHED URANIUM
LANTHANUM 140
MATHEMATICAL MODELS
MEASURING METHODS
PERFORMANCE
R CODES
REACTOR CONTROL SYSTEMS
REACTOR CORES
RESEARCH PROGRAMS
SLIGHTLY ENRICHED URANIUM
SPENT FUEL ELEMENTS
ACTINIDES
ALKALI METAL ISOTOPES
BETA DECAY RADIOISOTOPES
BETA-MINUS DECAY RADIOISOTOPES
CESIUM ISOTOPES
COMPUTER CODES
CONTROL SYSTEMS
DATA
DAYS LIVING RADIOISOTOPES
ELEMENTS
ENRICHED URANIUM
ENRICHED URANIUM REACTORS
FUEL SCANNING
GAMMA RADIOGRAPHY
INDUSTRIAL RADIOGRAPHY
INFORMATION
INTERMEDIATE MASS NUCLEI
ISOTOPE ENRICHED MATERIALS
ISOTOPES
LANTHANUM ISOTOPES
MATERIALS
METALS
NUCLEI
NUMERICAL DATA
ODD-EVEN NUCLEI
ODD-ODD NUCLEI
RADIOACTIVE MATERIALS
RADIOISOTOPES
RARE EARTH ISOTOPES
RARE EARTH NUCLEI
REACTOR COMPONENTS
REACTORS
SIMULATION
TANK TYPE REACTORS
URANIUM
WATER COOLED REACTORS
WATER MODERATED REACTORS
YEARS LIVING RADIOISOTOPES
220600* - Nuclear Reactor Technology- Research
Test & Experimental Reactors
990220 - Computers
Computerized Models
& Computer Programs- (1987-1989)
990230 - Mathematics & Mathematical Models- (1987-1989)
050700 - Nuclear Fuels- Fuels Production & Properties