Preliminary design of a graphite irradiation tensile creep experiment in the target region of the high flux isotope reactor

Journal of Nuclear Materials

Volumn 381, Issue 1-2, 2008, Pages 119-123

  McDuffee, J L ^a   Burchell, T D ^a   Heatherly, D W ^a   Thoms, K R ^a  

^a BATTELLE MEMORIAL INSTITUTE   (United States)

Author keywords

[No Author keywords available]

Indexed keywords

CARBON; CREEP; GRAPHITE; ISOTOPES; NUCLEAR MATERIALS SAFEGUARDS;

FLUENCES; HIGH FLUX ISOTOPE REACTORS; IRRADIATION TEMPERATURES; PRELIMINARY DESIGNS; TARGET REGIONS; TENSILE CREEP; TENSILE CREEP TESTS;

IRRADIATION;

EID: 54149092720     PISSN: 00223115     EISSN: None     Source Type: Journal    
DOI: 10.1016/j.jnucmat.2008.07.031     Document Type: Article

References (4)

1. Oku T., Fujisaki K., and Eto M. J. Nucl. Mater. 152 (1988) 223
2. Everett M.R., et al. J. Nucl. Mater. 65 (1977) 107
3. B.T. Kelly, A Feasibility Study for an Irradiation Creep Experiment on AGR Moderator Graphite, AEA Thermal Reactor Services, AEA TRA 5083, March 1991.
4. J.A. Vreeling et al., in: Sixth International Nuclear Graphite Specialists Meeting, Chamonix, September 2005.