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Postirradiation recovery of a reactor pressure vessel steel investigated by positron annihilation and microhardness measurements

Journal Article · · Nuclear Technology; (United States)
OSTI ID:5889260
 [1]; ; ;  [2]
  1. Univ. Carlos III de Madrid, Madrid (Spain)
  2. Univ. Complutense, Madrid (Spain)
Positron lifetime and microhardness measurements have been performed on untreated, thermal-aged, neutron-irradiated, and postirradiation-annealed samples of reactor pressure vessel steels with the purpose of investigating the mechanisms of irradiation-induced hardening and recovery of the mechanical properties in these materials. The positron lifetime experiments have not revealed any evidence of the formation of a significant concentration of voids or vacancy clusters in samples irradiated at [approximately]290 C with fluences [le]2.71 [times] 10[sup 23] n/m[sup 2] (E[gt]1 MeV), but they suggest a dislocation annealing induced by the irradiation. Isochronal annealing experiments with neutron-irradiated samples show a simultaneous recovery in their positron lifetime and microhardness at [approximately]340 C. From the microhardness measurements, the yield strength of the irradiated material has been estimated. The results appear to be consistent with a model of hardening due to irradiation-induced dissolution of precipitates with formation of small metastable precipitates after postirradiation aging and recovery induced by the disappearance of these metastable precipitates.
OSTI ID:
5889260
Journal Information:
Nuclear Technology; (United States), Journal Name: Nuclear Technology; (United States) Vol. 104:1; ISSN 0029-5450; ISSN NUTYBB
Country of Publication:
United States
Language:
English