Nondestructive examination of 54 fuel and reflector elements from Fort St. Vrain core segment 2

Technical Report · Fri Oct 01 00:00:00 EDT 1982

DOI:https://doi.org/10.2172/6811927· OSTI ID:6811927

Saurwein, J J

Fifty-four fuel and reflector elements irradiated in core segment 2 of the Fort St. Vrain high-temperature gas-cooled reactor (HTGR) were nondestructively examined. The time- and volume-averaged graphite irradiation temperatures for the elements ranged from approx. 350/sup 0/ to 750/sup 0/C. The element-averaged fast neutron fluences ranged from approx. 0.2 to 1.6 x 10/sup 25/ n/m/sup 2/ (E > 29 fJ)/sub HTGR/. The elements, except for two fuel elements in which single localizeed cracks developed during irradiation, were in excellent condition. No evidence was observed of significant graphite oxidation or mechanical interaction beween elements. The cracks in the two elements did not affect their performance or handling. These elements were, otherwise, in excellent condition. Nearly all elements shrank in both the axial and radial directions, but the dimensional changes were relatively small.

• Research Organization: General Atomics, San Diego, CA (United States)
• DOE Contract Number: AT03-76ET35300
• OSTI ID: 6811927
• Report Number(s): GA-A-16829; ON: DE83005992
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
VRAIN REACTOR
FUEL RODS
BURNUP
INSPECTION
NONDESTRUCTIVE TESTING
PERFORMANCE TESTING
REACTOR CORES
STRAINS
ENRICHED URANIUM REACTORS
FUEL ELEMENTS
GAS COOLED REACTORS
GRAPHITE MODERATED REACTORS
HELIUM COOLED REACTORS
HTGR TYPE REACTORS
MATERIALS TESTING
POWER REACTORS
REACTOR COMPONENTS
REACTORS
TESTING
210300* - Power Reactors
Nonbreeding
Graphite Moderated