Demonstration of a high burnup heterogeneous core using ferritic/martensitic materials

Conference · Fri Apr 11 04:00:00 EST 1986

OSTI ID:6428000

Lovell, A J; Fox, G L; Sutherland, W H; Hecht, S L

The purpose of the Core Demonstration Experiment (CDE) is to demonstrate the capability of a mixed-oxide fuel system to achieve a three year life in a prototypic LMR heterogeneous reactor environment. The CDE assemblies are fabricated using wire-wrapped, large-diameter, advanced-oxide fuel and blanket pins with tempered martensitic HT9 cladding, wire wrap, and duct. The highest power fuel assembly operates with a Beginning of Life (BOL) peak linear pin power of 445 W/cm and a peak cladding temperature of 615C. The fuel and blanket assembly irradiation will start in FFTF Cycle 9 and continue for about 900 Equivalent Full Power Days (EFPD). The successful utilization of the tempered martensitic HT9 alloy in an FFTF test assembly is fully anticipated. The low swelling, observed at intermediate neutron fluence and projected to higher fluences, together with reasonable creep behavior gives acceptable mechanical performance for fuel pins, blanket pins and ducts. Duct length increase, dilation and bow; plus fuel and blanket pin diameter increases remain within specified tolerances. In addition, stress rupture data from unirradiated HT9 imply cumulative damage fractions for the nominal fuel and blanket pins that are low.

• Research Organization: Hanford Engineering Development Lab., Richland, WA (USA)
• DOE Contract Number: AC06-76FF02170
• OSTI ID: 6428000
• Report Number(s): HEDL-SA-3491; CONF-860931-23; ON: DE87009966
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210500* -- Power Reactors
Breeding
36 MATERIALS SCIENCE
360106 -- Metals & Alloys-- Radiation Effects
ALLOY-HT-9
ALLOYS
BREEDER REACTORS
BURNUP
CHROMIUM ALLOYS
CHROMIUM STEELS
CHROMIUM-MOLYBDENUM STEELS
DATA
EPITHERMAL REACTORS
EXPERIMENTAL DATA
FAST REACTORS
FBR TYPE REACTORS
FUEL ASSEMBLIES
FUEL CANS
FUELS
HETEROGENEOUS REACTOR CORES
INFORMATION
IRON ALLOYS
IRON BASE ALLOYS
IRRADIATION
LIQUID METAL COOLED REACTORS
LMFBR TYPE REACTORS
MIXED OXIDE FUELS
NEUTRON FLUX
NUMERICAL DATA
PHYSICAL RADIATION EFFECTS
RADIATION EFFECTS
RADIATION FLUX
REACTOR COMPONENTS
REACTOR CORES
REACTORS
SOLID FUELS
STEELS
SWELLING