Evaluation of surface modification techniques for PWR steam generator channel heads. Final report
Surface modification which were developed under a previous EPRI program and then applied to Boiling Water Reactor replacement piping, were modified for treating PWR steam generator channel head surfaces. Surface modifications have been shown to reduce out-of-core activity build up in BWR and thought to be equally effective in PWR circuits as well. Prototypical surface test specimens were used to develop techniques appropriate to PWR alloy substrates which were then applied to treat the surfaces of a spare, full size PWR channel head in a field demonstration. Modified surfaces cut from test specimens and pieces removed from the field demonstration were submitted to metallurgical investigations. No damage to the substrate alloys was detected as a result of the surface modification processes. Combination of mechanical and electropolishing action improved the as fabricated finish by at least a factor of 3 for the Inconel plate and factors of 20 for the stainless weld overlay. Field demonstration yielded a factor of 10 improvement in the weld overlay and 30 to 40% in the divider plate. Because these surfaces are known to be responsible for 57% of the area radioactivity in PWR steam generators in service, prepolishing is expected to reduce radiation fields substantially. 31 figs.
- Research Organization:
- Quadrex Corp., Campbell, CA (USA)
- OSTI ID:
- 5826743
- Report Number(s):
- EPRI-NP-4614; ON: TI86920332; TRN: 86-018783
- Country of Publication:
- United States
- Language:
- English
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PWR TYPE REACTORS
STEAM GENERATORS
MODIFICATIONS
EVALUATION
RADIATION DOSES
RADIATION PROTECTION
REACTOR MATERIALS
SURFACE TREATMENTS
WATER CHEMISTRY
BOILERS
CHEMISTRY
DOSES
MATERIALS
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VAPOR GENERATORS
WATER COOLED REACTORS
WATER MODERATED REACTORS
210200* - Power Reactors
Nonbreeding
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