Effect of venting on crevice cleaning for PWR steam generators. Final report

Technical Report · Thu May 01 04:00:00 EDT 1986

OSTI ID:5693791

Parke, J M; Schneidmiller, D; Olson, P M

Process parameters affecting chemical cleaning of tube-to-support plate crevice annuli in dented PWR steam generators were investigated. A simple procedural modification to the generic SGOG crevice cleaning process was identified which assures that support plate crevices can be consistently cleaned within reasonable guidelines for solvent contact time (under test conditions). The key parameter affecting crevice cleaning rates was identified as strong solvent agitation due to near-surface boiling during system venting. For actual application, the solvent level in the steam generator must be adjusted to be just above the support plate to be cleaned and the steam generator vented periodically to reduce pressure to induce near-surface boiling in the solvent. 13 figs., 12 tabs.

• Research Organization: Pacific Nuclear Services, Richland, WA (USA)
• OSTI ID: 5693791
• Report Number(s): EPRI-NP-4600; ON: TI86920297
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210200* -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
36 MATERIALS SCIENCE
360105 -- Metals & Alloys-- Corrosion & Erosion
BOILERS
CHEMICAL REACTIONS
CLEANING
CORROSION
CREVICE CORROSION
EVALUATION
PWR TYPE REACTORS
REACTORS
STEAM GENERATORS
TESTING
VAPOR GENERATORS
WATER COOLED REACTORS
WATER MODERATED REACTORS