Extended Fuel-Burnup Demonstration Program. Semi-annual technical progress report, July 1981-December 1981

Technical Report · Mon Mar 01 04:00:00 EST 1982

OSTI ID:5278107

Moss, H D ^[1]

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1. comp.

The feasibility of increasing the region average discharge burnup of pressurized water reactor (PWR) fuel assemblies to values exceeding 40,000 MWD/MTU is studied. For the 3-loop 15 x 15 assembly plant, the loading arrangement for the second transition cycle has been determined. It uses a feed of 60 fresh assemblies at an average enrichment of 3.81%. A low leakage loading pattern and wet annular burnable absorbers were utilized. Also, the loading arrangement for the third transition cycle has been determined. It consists of 56 feed assemblies. The fourth irradiation cycle of the Westinghouse 17 x 17 demonstration fuel assembly RD-2, in the VEPCO Surry Unit 2 reactor was completed on 7 November 1981. The assembly had attained a burnup of 42,511 MWD/MTU by that date. A mini-site examination, consisting of both low and high magnification TV Scans and fuel assembly length measurements, was performed the first week of December 1981. Fuel assembly RD-2 showed no anomalies, no channel closures and no heavy crud or corrosion.

• Research Organization: Virginia Electric and Power Co., Richmond (USA); Westinghouse Electric Corp., Pittsburgh, PA (USA). Nuclear Energy Systems Div.
• DOE Contract Number: AC02-79ET34014
• OSTI ID: 5278107
• Report Number(s): DOE/ET/34014-T1; ON: DE82018735
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210200* -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
BURNUP
FUEL ASSEMBLIES
FUEL MANAGEMENT
INSPECTION
PERFORMANCE TESTING
PWR TYPE REACTORS
REACTOR COMPONENTS
REACTOR CORES
REACTORS
TESTING
WATER COOLED REACTORS
WATER MODERATED REACTORS