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PROCEEDINGS OF THE TWENTY-FOURTH WATER REACTOR SAFETY INFORMATION MEETING.Reactor Pressure Vessel Embrittlement And Thermal Annealing,Reactor Vessel Lower Head Integrity And Evaluation And Projection of Steam Generator tube....

Accession Number Link: ML20136D157 (444 page(s))

Date Released: Wednesday, February 28, 2024

Document Type: CONFERENCE & WORKSHOP PAPERS/PROCEEDINGS/ABSTRACTS, NUREG REPORTS, TEXT-SAFETY REPORT

Author Name: MONTELEONE S

Author Affiliation: BROOKHAVEN NATIONAL LABORATORY

Addressee Affiliation: NRC OFFICE OF NUCLEAR REGULATORY RESEARCH (RES)

Case/Reference Number: CON-FIN-A-3988

Document/Report Number: NUDOCS 9703120276, NUREG-CP-0157, NUREG-CP-0157-V02, NUREG-CP-157, NUREG-CP-157-V2

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