Properties of irradiated and periodically annealed graphite

Journal Article · Tue Oct 01 04:00:00 EDT 1963 · Nuclear Science and Engineering

OSTI ID:4157130

Aronson, Seymour; Schweitzer, D. G.; Singer, R. M.

Samples of AG0T nuclear grade graphite were irradiated with neutrons at 30-40 deg C for 200-240 Mwd/at. of uranium. The samples were temporarily removed from the reactor at regular intervals and annealed at 350 deg C for 1-4 hrs. They were also annealed after the final irradiation. Dimensional, C-axis, electric conductivity, Hall coefficient, thermal conductivity, and stored energy data were obtained using standard techniques on samples cut perpendicular to the extrusion axis of the graphite bar. (C.E.S.)

• Research Organization: Brookhaven National Lab., Upton, NY (United States)
• Sponsoring Organization: US Atomic Energy Commission (AEC)
• DOE Contract Number: AT(30-2)-GEN-16
• NSA Number: NSA-18-000662
• OSTI ID: 4157130
• Report Number(s): BNL--6882; 0025-5639
• Journal Information: Nuclear Science and Engineering, Journal Name: Nuclear Science and Engineering Journal Issue: 2 Vol. 17; ISSN 0029-5639; ISSN NSENA
• Publisher: Academic Press
• Country of Publication: United States
• Language: English

Related Subjects

AGOT GRAPHITE
ANNEALING
CONFIGURATION
ELECTRIC CONDUCTIVITY
ENERGY
EXTRUSION
GRAPHITE
HALL EFFECT
IMPURITIES
IRRADIATION
METALS, CERAMICS, AND OTHER MATERIALS
NEUTRON BEAMS
RODS
SAMPLING
STANDARDS
STORAGE
TEMPERATURE
THERMAL CONDUCTIVITY
THICKNESS
URANIUM