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The 250-MW, boiling-water Gundremmingen reactor KRB-A in the Federal Republic of Germany (FRG) has been decommissioned. A joint USA/FRG/UK study, conceived by the U.S. Nuclear Regulatory Commission (NRC), is underway to evaluate material removed from the vessel for a critical assessment of power reactor versus test reactor environment effects. The vessel operated at ∼288°C; the inner-wall fluence estimate at decommissioning was about
This report describes test reactor irradiation assessments of a forging segment believed to be archive material from the KRB-A vessel fabrication. Charpy-V (
The L-C orientation data for the archive material versus the vessel trepans suggest a fluence-rate effect. However, the C-L orientation data do not. A test orientation dependence of radiation embrittlement sensitivity, described by the trepan material, but not the archive material, is responsible and is anomalous.
Gundremmingen KRB-A reactor, pressure vessels, radiation embrittlement, notch ductility, fracture toughness, neutron dosimetry, 20NiMoCr26 steel, A336 steel, test reactor, Charpy-V test, compact tension test, postirradiation annealing, J-R curve, fluence rate effects
Hawthorne, J. Russell
Senior metallurgist, Materials Engineering Associates, Inc., Lanham, MD
Hiser, Allen L.
Engineer, Materials Engineering Associates, Inc., Lanham, MD