Published September 2012 | Version v1
Miscellaneous Open

Effect of Low DH Concentration on Crud Deposition on Heated Zircaloy-4 in Simulated PWR Primary Water

Description

In order to mitigate PWSCC initiation and propagation of Ni base alloy, Japanese PWR utilities desire to employ optimized dissolved hydrogen (DH) control operation in the near future. Prior to the application of the optimized DH control operation to PWR, the effect of DH concentration on the fuel crud deposition should be clarified. Crud deposition tests were carried out in 1200 ppm as B + 2.2 ppm as Li + 5 to 25 cm3.STP/kg.H2O solutions at 325 deg. C under sub-cooled boiling and non-irradiated condition. The corrosion resistance of zircaloy-4 was also investigated. From the test results, it was revealed that the crud layer composed of NiFe2O4 and NiO was formed on zircaloy-4 fuel cladding. NiO was easy to form in the crud layer under the 5 and 7 cm3.STP/kg.H2O condition. The amounts of deposited crud layer, boron contents incorporated into the crud layer and the corrosion resistances of cladding were not affected by DH concentration. (authors)

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Additional details

Publishing Information

Imprint Pagination
37 p.
Report number
NPC--2012-002

Conference

Title
Nuclear Plant Chemistry Conference, International Conference on Water Chemistry of Nuclear Reactor Systems
Acronym
NPC 2012
Dates
23-27 Sep 2012
Place
Paris (France)

Optional Information

Notes
15 Refs.; Available from the INIS Liaison Officer for France, see the 'INIS contacts' section of the INIS website for current contact and E-mail addresses: http://www.iaea.org/inis/Contacts/