Published March 1992 | Version v1
Report Metadata-only

Effect of lithium hydroxide on zircaloy corrosion in the Ringhals-3 PWR plant

Creators

  • 1. Nuclear Electric plc, Berkeley (United Kingdom). Berkeley Nuclear Labs.
  • 2. Statens Vattenfallsverk, Stockholm (Sweden)

Description

Zircaloy oxide thicknesses were predicted for several fuel rods irradiated in Ringhals 3 over cycles 1b-4. During most of this period the fuel cladding was exposed to a high pH primary coolant chemistry regime in which lithium was present up to a concentration of 3.5 ppm. Comparison of prediction with measurement showed that the presence of lithium had produced no enhancement in oxidation within the limits of experimental and computational error

Availability note (English)

Research Reports Center, PO Box 50490, Palo Alto, CA 94303.

Additional details

Additional titles

Subtitle (English)
Final report

Publishing Information

Imprint Pagination
83 p.
Report number
EPRI-TR--100389

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
23054355
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Non-conventional Literature
Descriptors DEI
BUILDUP; CORROSION; CORROSIVE EFFECTS; FUEL CANS; LITHIUM HYDROXIDES; OXIDES; RINGHALS-3 REACTOR; THICKNESS; WATER CHEMISTRY; ZIRCALOY
Descriptors DEC
ALKALI METAL COMPOUNDS; ALLOYS; CHALCOGENIDES; CHEMICAL REACTIONS; CHEMISTRY; DIMENSIONS; ENRICHED URANIUM REACTORS; HYDROGEN COMPOUNDS; HYDROXIDES; LITHIUM COMPOUNDS; OXYGEN COMPOUNDS; POWER REACTORS; PWR TYPE REACTORS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS; ZIRCONIUM ALLOYS; ZIRCONIUM BASE ALLOYS

Optional Information

Funding organization
Electric Power Research Inst., Palo Alto, CA (United States).