IRRADIATION OF HIGH-DENSITY GRAPHITE THERMAL CONDUCTIVITY SPECIMENS IN CAPSULE ATC 2-1 IN THE MATERIALS TESTING REACTOR

Technical Report · Fri Feb 14 04:00:00 EST 1958

OSTI ID:4287564

Lee, D; Foster, G; Gabay, J

The development and fabrication of a capsule suitable for the irradiation of graphite specimens in the Materials Testing Reactor (MTR) at Idaho Falls, Idaho, under conditions of a constant sample temperature of 750 deg F (400 deg C) at maximum fast neutron fiux in an oxygenfree helium atmosphere are described. The test data of primary interest were specimen temperatures, total integrated neutron flux, and nonthermal neutron flux. Great care was taken to avoid damage to the graphite specimens, in order not to invalidate the comparison of post-irradiation data with the elaborate pre-irradiation measurements of weight, dimensions, and thermial conductivity which had been made at BNL. (auth)

• Research Organization: Nuclear Development Corp. of America, White Plains, N.Y.
• DOE Contract Number: AT(30-2)-GEN-16
• NSA Number: NSA-13-000924
• OSTI ID: 4287564
• Report Number(s): NDA-9018-1
• Country of Publication: United States
• Language: English

Related Subjects

BLOOD CELLS
CANCER
CAPSULES
DENSITY
DISEASES
FAST NEUTRONS
GRAPHITE
HELIUM
HYPERTHYROIDISM
IODINE ISOTOPES
LEUKEMIA
MAN
MECHANICAL PROPERTIES
MEDICINE
MTR
NEUTRON FLUX
OXYGEN
PHOSPHORUS 32
PREPARATION
RADIATION DOSES
RADIATION EFFECTS
RADIATION EFFECTS ON MATERIALS
RADIOISOTOPES
RADIOTHERAPY
REACTORS
TEMPERATURE
THERMAL CONDUCTIVITY
THYROID
USES