The behavior of a B/sub 4/C-phenolic and a glass-fiber-reinforced B/sub 4/C-phenolic composite in a spent nuclear fuel storage pool

Journal Article · Mon Nov 01 00:00:00 EST 1982 · Nucl. Technol.; (United States)

OSTI ID:6819169

Macmillan, N H; Dooher, G I; Naum, R G

A three-part experimental study has been carried out to determine the effects of exposure to the spent nuclear fuel pool environment on two composite neutron-absorbing materials--one made in plate form and consisting of about 72 wt% of B/sub 4/C particles bonded together by about 28 wt% of a phenol-formaldehyde polymer, and the other made in sheet form and consisting of about 62 wt% of B/sub 4/C particles bonded to both sides of a woven glass-fiber reinforcement by about 19 wt% of the same polymer. The results of the mechanical and physical properties tests show that the two materials degrade somewhat differently in the spent fuel pool environment. In the case of the plate material, radiation-induced expansion and embrittlement of the polymer lead at doses about 10/sup 9/ Gy to about 1% linear expansion, with a concomitant about 60% reduction in strength and stiffness and a somewhat enhanced sus-

• Research Organization: The Pennsylvania State University Materials Research Laboratory, University Park, Pennsylvania 16802
• OSTI ID: 6819169
• Journal Information: Nucl. Technol.; (United States), Vol. 59:2
• Country of Publication: United States
• Language: English

Related Subjects

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
36 MATERIALS SCIENCE
BORON CARBIDES
CHEMICAL RADIATION EFFECTS
MATERIALS TESTING
PHYSICAL RADIATION EFFECTS
FUEL POOLS
NEUTRON ABSORBERS
BORON OXIDES
CARBON DIOXIDE
COMPOSITE MATERIALS
EMBRITTLEMENT
EXPANSION
EXPERIMENTAL DATA
FORMALDEHYDE
GLASS
HYDROGEN
LEACHING
MECHANICAL PROPERTIES
PHENOLS
PHYSICAL PROPERTIES
RADIATION DOSES
REINFORCED MATERIALS
SPENT FUEL STORAGE
ALDEHYDES
AROMATICS
BORON COMPOUNDS
CARBIDES
CARBON COMPOUNDS
CARBON OXIDES
CHALCOGENIDES
CHEMISTRY
DATA
DISSOLUTION
DOSES
ELEMENTS
HYDROXY COMPOUNDS
INFORMATION
MATERIALS
NONMETALS
NUMERICAL DATA
ORGANIC COMPOUNDS
OXIDES
OXYGEN COMPOUNDS
RADIATION CHEMISTRY
RADIATION EFFECTS
SEPARATION PROCESSES
STORAGE
TESTING
050900* - Nuclear Fuels- Transport
Handling
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360206 - Ceramics
Cermets
& Refractories- Radiation Effects