Thermal Utilization Measurement
- Brookhaven National Laboratory (BNL), Upton, NY (United States)
An intra cell neutron flux traverse has been done in the BNL reactor by the Reactor Physics group, to measure thermal utilization. A special uranium fuel element was constructed with provision for containing 25 dysprosium foils internally and 12 dysprosium foils on the aluminum fins. The fuel element was 3 feet long and was constructed of the same materials which are normally used in the reactor fuel elements and was loaded into fuel channel A-9-6. A special graphite cartridge, 2.6" diameter and 2 feet long, was loaded into newsom hole A-9-6 1/2. Dysprosium foils were embedded in the graphite cartridge opposite the foils in the special fuel element. The distribution of dysprosium foils permitted a measurement of neutron flux in the uranium, on the aluminum fins, and in the graphite midway between nearest fuel rods.
- Research Organization:
- Brookhaven National Laboratory (BNL), Upton, NY (United States)
- Sponsoring Organization:
- USDOE National Nuclear Security Administration (NNSA), Nuclear Criticality Safety Program (NCSP); US Atomic Energy Commission (AEC)
- DOE Contract Number:
- AC02-76CH00016
- NSA Number:
- NSA-10-003866
- OSTI ID:
- 4358571
- Report Number(s):
- BNL-1992
- Country of Publication:
- United States
- Language:
- English
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