Skip to main content
U.S. Department of Energy
Office of Scientific and Technical Information

POWER DISTRIBUTION MEASUREMENTS OF CLAD ELEMENTS IN THE ATRCE CORE

Technical Report ·
OSTI ID:4749258

Flux distribution measurements were made in the Advanced Test Reactor Critical Experiment Core containing 10 clad and 30 unclad fuel elements to assist in the ATR design and provide experimental data for comparison with nuclear calculations. With reactor conditsons of three and six neck shim rods per neck, flux distribution measurements in the 40 elements, radial measurements in elements 1 to 5, and circumferential measurements in clad element No. 3 were taken. Dysprosium-aluminum foils measured the distributions around the core, but uraniumaluminum foils were used for the fine structure measurements. The average activity in the eight elements that comprised lobe 7 was approximately 50% higher than that in lobe 3 containing the clad fuel elements. Boron-mylar tape attached to the unclad elements reduced the flux shift to approximately 3%. Under the condition of six shim rods per neck, a power-split was not determined because of large flux shift. Utilizing three shim rods per neck, a power-split of 40-65-64 was found. There was little difference between the uranium and dysprosium traverses under the same reactor conditions. The radial, peak-toaverage, power generation rate was 1.98 in the experimental core with no corrections for temperature effects, burnable poison distribution, or the increased fuel loading of the actual ATR Core. (auth)

Research Organization:
Babcock and Wilcox Co. Critical Experiment Lab., Lynchburg, Va.
NSA Number:
NSA-17-015502
OSTI ID:
4749258
Report Number(s):
TID-18029; ATRCE-108
Country of Publication:
United States
Language:
English

Similar Records

FLUX DISTRIBUTIONS IN UNBALANCED ATRCE REFERENCE CORES
Technical Report · Mon Oct 01 00:00:00 EDT 1962 · OSTI ID:4772184

Axial effects of xenon-samarium poisoning in the advanced test reactor
Conference · Sun Dec 31 23:00:00 EST 1989 · Transactions of the American Nuclear Society; (United States) · OSTI ID:7089212

Thermal Utilization Measurement
Technical Report · Thu Aug 19 00:00:00 EDT 1954 · OSTI ID:4358571