Inspecting the reactor vessel penetrations

Conference · Tue Aug 01 04:00:00 EDT 1995

OSTI ID:86170

Bodson, F ^[1]; Fleming, K W ^[2]

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1. Framatome, Chalon-Sur-Saone (France)
2. BWNT, Lynchburg, VA (United States)

The susceptibility of Alloy 600 to Primary Water Stress Corrosion Cracking (PWSCC) continues to plague nuclear power plants. Recently, the problem of PWSCC cracking has manifested itself in Control Rod Drive Mechanism (CRDM) head penetrations in nuclear plants in Europe. Framatome has been extensively involved in the performance of both inspections and repairs of CRDM head penetrations at Electricite de France (EdF) plants. B and W Nuclear Technologies (BWNT), building on Framatome technology, has developed a fully integrated service package and robotic manipulator to inspect and repair CRDM head penetrations for US utilities. Reactor vessel bottom penetration are also made of Alloy 600 and to tackle this potential PWSCC problem at EdF plants, Framatome has been performing specific inspections in order to detect the appearance of the phenomenon. This paper describes the overall range of inspection techniques and toolings developed to address these issues.

• OSTI ID: 86170
• Report Number(s): CONF-9505104--; ISBN 0-87170-548-6
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
22 GENERAL STUDIES OF NUCLEAR REACTORS
36 MATERIALS SCIENCE
CONTROL ROD DRIVES
CRACK PROPAGATION
IN-SERVICE INSPECTION
INCONEL 600
NONDESTRUCTIVE TESTING
OPENINGS
PRESSURE VESSELS
PRIMARY COOLANT CIRCUITS
PWR TYPE REACTORS
REACTOR MATERIALS
STRESS CORROSION