Gamma-scan measurements at Edwin I. Hatch Nuclear Plant Unit 1 following Cycle 3. Final report

Technical Report · Fri Jul 01 00:00:00 EDT 1983

OSTI ID:5350529

Kosanke, H D; Gregory, M C; Ma, J T; Crawford, B W

A major measurement program to obtain relative La-140 (Ba-140) gamma-ray intensities for irradiated fuel bundles and rods, reflective of recent fission distributions, was performed at Edwin I. Hatch Nuclear Plant Unit 1 during the refueling and maintenance outage following Cycle 3. This report describes the measurement program, and presents the gamma-scan data in terms of the relative La-140 intensities for discrete elevations along the fuel axis. The total random uncertainties for the measurements were determined to be less than or equal to 1.3% (1 sigma) for most bundle four-corner-averaged intensities and less than or equal to 2.0% (1 sigma) for most single fuel-rod nodal intensities. A practical accuracy of 3% (1 sigma) was implied for the reported distributions from the combination of measurement uncertainties and methods biases.

• Research Organization: General Electric Co., San Jose, CA (USA). Nuclear Energy Engineering Div.
• OSTI ID: 5350529
• Report Number(s): EPRI-NP-2105; ON: DE84920004
• Country of Publication: United States
• Language: English

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