Feasibility of and methodology for thermal annealing an embrittled reactor vessel. Volume 2. Detailed technical description of the work. Final report
Technical Report
·
OSTI ID:6886517
Program materials were three weldments fabricated from A533 Grade B class 1 plate material and Mn Mo Ni weld wire. Specimens fabricated from the three submerged arc weldments included Type A Charpy V-notch impact, small size tensile, and 1/2T compact tension specimens. After encapsulation, the specimens were irradiated at the UVAR to two fluence levels, 8 x 10/sup 18/ n/cm/sup 2/ and 1.5 x 10/sup 19/ n/cm/sup 2/ (E > 1 MeV). Specimens were subjected to sequences of irradiation and anneals and then tested. Metallurgial/mechanistic analyses were also performed. It was concluded that excellent recovery of all properties could be achieved by annealing at greater than or equal to 850/sup 0/F (454/sup 0/C) for 168 hours. Such an annealing resulted in ductile-brittle transition temperature shift recovery of 80 to 100%, and reirradiation after this annealing indicated that the ductile-brittle transition temperature shift appears to continue at the expected rate. Several drawbacks were identified for wet thermal annealing. A conceptual dry in-situ thermal annealing procedure was developed for thermal annealing embrittled reactor vessels.
- Research Organization:
- Westinghouse Electric Corp., Pittsburgh, PA (USA). Nuclear Technology Div.
- OSTI ID:
- 6886517
- Report Number(s):
- EPRI-NP-2712-Vol.2; ON: DE83900744
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
22 GENERAL STUDIES OF NUCLEAR REACTORS
220200* -- Nuclear Reactor Technology-- Components & Accessories
36 MATERIALS SCIENCE
360106 -- Metals & Alloys-- Radiation Effects
ALLOYS
ANNEALING
BARYONS
CONTAINERS
DATA
DUCTILE-BRITTLE TRANSITIONS
ELEMENTARY PARTICLES
EMBRITTLEMENT
EXPERIMENTAL DATA
FAST NEUTRONS
FERMIONS
FRACTURE PROPERTIES
HADRONS
HEAT TREATMENTS
INFORMATION
IRON ALLOYS
IRON BASE ALLOYS
JOINTS
MATERIALS TESTING
MECHANICAL PROPERTIES
METALLURGY
NEUTRONS
NUCLEONS
NUMERICAL DATA
PHYSICAL RADIATION EFFECTS
RADIATION EFFECTS
REACTOR VESSELS
STEEL-ASTM-A533
STEELS
TESTING
WELDED JOINTS
220200* -- Nuclear Reactor Technology-- Components & Accessories
36 MATERIALS SCIENCE
360106 -- Metals & Alloys-- Radiation Effects
ALLOYS
ANNEALING
BARYONS
CONTAINERS
DATA
DUCTILE-BRITTLE TRANSITIONS
ELEMENTARY PARTICLES
EMBRITTLEMENT
EXPERIMENTAL DATA
FAST NEUTRONS
FERMIONS
FRACTURE PROPERTIES
HADRONS
HEAT TREATMENTS
INFORMATION
IRON ALLOYS
IRON BASE ALLOYS
JOINTS
MATERIALS TESTING
MECHANICAL PROPERTIES
METALLURGY
NEUTRONS
NUCLEONS
NUMERICAL DATA
PHYSICAL RADIATION EFFECTS
RADIATION EFFECTS
REACTOR VESSELS
STEEL-ASTM-A533
STEELS
TESTING
WELDED JOINTS