PWR full-reactor coolant system decontamination. Materials evaluation after off-normal exposure to the LOMI decontamination process, Final report

Technical Report · Wed Jan 01 04:00:00 EST 1992

OSTI ID:10118970

Aspden, R G; Pessall, N; Grand, T F ^[1]

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1. Westinghouse Electric Corp., Pittsburgh, PA (United States)

The overall objective of the current program is to identify and address all aspects of full system decontamination with the purpose of qualifying at least one process for PWR use. The objective of the current study is to provide baseline data on the performance of materials on the primary side after exposure to one cycle of the LOMI fault testing. This data supplements prior information obtained after exposure to three cycles of LOMI testing. The technical significance of this excursion will be determined in a subsequent task. The general corrosion characteristics of over 39 materials were evaluated for some combinations of material, type of specimen (coupon and creviced coupons), and loop velocity (0, 5, 20 and 150 ft/sec). At velocities of less than or equal to 20 ft/sec, sixteen types of specimens were employed to evaluate localized corrosion and stress corrosion cracking. Specimens were examined after one cycle. Also included in this exposure were specimens added to provide more information on the effect of LOMI fault exposure one: (1) surface roughening of Stellite 156; (2) crevice corrosion of chromium plated 304 stainless steel with the open end gap increased from 3 to {approximately} 9 mils; (3) susceptibility of Inconel X-750 (HTH) to subsequent stress corrosion cracking, (4) loss of chromium plate from threads of 304 stainless steel bolts torqued into stainless steel collars; (5) crack initiation in an Alloy 600 tube known to be susceptible to primary water stress corrosion cracking; and (6) surface alternation of stressed Inconel X-750 springs with the spring temper.

• Research Organization: Electric Power Research Inst., Palo Alto, CA (United States); Westinghouse Electric Corp., Pittsburgh, PA (United States)
• Sponsoring Organization: Electric Power Research Inst., Palo Alto, CA (United States)
• OSTI ID: 10118970
• Report Number(s): EPRI-NP--7513-M; ON: UN92007296
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210200
BUILDUP
CLEANING
CORROSION
CORROSION PRODUCTS
CRACKS
DECONTAMINATION
INCONEL X750
POWER REACTORS
NONBREEDING
LIGHT-WATER MODERATED
NONBOILING WATER COOLED
PWR TYPE REACTORS
RADIATION PROTECTION
REACTOR COOLING SYSTEMS
REACTOR MATERIALS
STAINLESS STEEL-304
STEAM GENERATORS
SURFACE PROPERTIES