{sup 252}Cf-source-correlated transmission measurements for uranyl fluoride deposit in a 24-in.-OD process pipe

Conference · Mon Jun 01 04:00:00 EDT 1998

OSTI ID:661665

Uckan, T; Mihalczo, J T; Valentine, T E; Mullens, J A ^[1]; Wyatt, M S ^[2]; Hannon, T F ^[3]

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1. Oak Ridge National Lab., TN (United States). Instrumentation and Controls Div.
2. Univ. of Tennessee, Knoxville, TN (United States). Dept. of Nuclear Engineering
3. Central Engineering Services, Oak Ridge, TN (United States)

Characterization of a hydrated uranyl fluoride (UO{sub 2}F{sub 2}{center_dot}nH{sub 2}O) deposit in a 17-ft-long, 24-in.-OD process pipe at the former Oak Ridge Gaseous Diffusion Plant was successfully performed by using {sup 252}Cf-source-correlated time-of-flight (TOF) transmission measurements. These measurements of neutrons and gamma rays through the pipe from an external {sup 2521}Cf fission source were used to measure the deposit profile and its distribution along the pipe, the hydration (or H/U), and the total uranium mass. The measurements were performed with a source in an ionization chamber on one side of the pipe and detectors on the other. Scanning the pipe vertically and horizontally produced a spatial and time-dependent radiograph of the deposit in which transmitted gamma rays and neutrons were separated in time. The cross-correlation function between the source and the detector was measured with the Nuclear Weapons Identification System. After correcting for pipe effects, the deposit thickness was determined from the transmitted neutrons and H/U from the gamma rays. Results were consistent with a later intrusive observation of the shape and the color of the deposit; i.e., the deposit was annular and was on the top of the pipe at some locations, demonstrating the usefulness of this method for deposit characterization.

• Research Organization: Oak Ridge National Lab., TN (United States)
• Sponsoring Organization: USDOE, Washington, DC (United States)
• DOE Contract Number: AC05-96OR22464; AC05-84OR21400
• OSTI ID: 661665
• Report Number(s): ORNL/CP--97879; CONF-980545--; ON: DE98003506
• Country of Publication: United States
• Language: English

Related Subjects

05 NUCLEAR FUELS
CALIFORNIUM 252
DEPOSITS
GAMMA RADIATION
HYDRATION
MEASURING METHODS
NEUTRONS
ORGDP
REMEDIAL ACTION
SAFETY
TIME-OF-FLIGHT METHOD
URANYL FLUORIDES