Preliminary data on processing and characterization of recycled irradiated graphite

Carbon

Volumn 48, Issue 11, 2010, Pages 3303-3305

  Pappano, Peter J ^a   Burchell, Timothy D ^a  

^a OAK RIDGE NATIONAL LABORATORY   (United States)

Author keywords

[No Author keywords available]

Indexed keywords

DATA HANDLING; PARTICLE SIZE; PARTICLE SIZE ANALYSIS; RECYCLING;

FLUENCES; IRRADIATED GRAPHITE; IRRADIATION TEMPERATURE; NEUTRON IRRADIATED; NUCLEAR GRAPHITE; OAK RIDGE NATIONAL LABORATORY; PROPERTY VALUE; RADIOLOGICAL FACILITY;

GRAPHITE;

EID: 78049527204     PISSN: 00086223     EISSN: None     Source Type: Journal    
DOI: 10.1016/j.carbon.2010.05.012     Document Type: Letter

References (2)

1. Burchell TD, Snead LL, Williams AM, Bailey JL, Strizak JP. Final post irradiation examination data report for SGL NBG-10 nuclear grade graphite. Pub Oak Ridge, USA, ORNL/TM/-2006/ 430; 2006.
2. Burchell TD, Snead LL. The effect of neutron irradiation damage on the properties of grade NBG-10 graphite. J Nucl Mater 2007;371:18-27. (Pubitemid 47247726)