Development of an extended-burnup Mark B design. First semi-annual progress report, July-December 1978. Report BAW-1532-1. [PWR]

Technical Report · Mon Oct 01 00:00:00 EDT 1979

DOI:https://doi.org/10.2172/5194213· OSTI ID:5194213

The primary objective of this program is to develop and demonstrate an improved PWR fuel assembly design capable of batch average burnups of 45,000-50,000 MWd/mtU. To accomplish this, a number of technical areas must be investigated to verify acceptable extended-burnup fuel performance. This report is the first semi-annual progress report for the program, and it describes work performed during the July-December 1978 time period. Efforts during this period included the definition of a preliminary design for a high-burnup fuel rod, physics analyses of extended-burnup fuel cycles, studies of the physics characteristics of changes in fuel assembly metal-to-water ratios, and development of a design concept for post-irradiation examination equipment to be utilized in examining high-burnup lead-test assemblies.

• Research Organization: Babcock and Wilcox Co., Lynchburg, VA (USA)
• Sponsoring Organization: USDOE
• DOE Contract Number: AC02-78ET34213
• OSTI ID: 5194213
• Report Number(s): DOE/ET/04712-1; TRN: 80-013466
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
FUEL ASSEMBLIES
BURNUP
PERFORMANCE
PWR TYPE REACTORS
CREEP
FUEL MANAGEMENT
FUEL RODS
POWER DENSITY
POWER DISTRIBUTION
PRESSURE GRADIENTS
STRESSES
URANIUM DIOXIDE
ZIRCONIUM OXIDES
ACTINIDE COMPOUNDS
CHALCOGENIDES
FUEL ELEMENTS
MECHANICAL PROPERTIES
OXIDES
OXYGEN COMPOUNDS
REACTOR COMPONENTS
REACTORS
TRANSITION ELEMENT COMPOUNDS
URANIUM COMPOUNDS
URANIUM OXIDES
WATER COOLED REACTORS
WATER MODERATED REACTORS
ZIRCONIUM COMPOUNDS
210200* - Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled