Published 2010 | Version v1
Book

Relevance of alumina grit analysis in zircaloy fabrication process

  • 1. Control Laboratory, Nuclear Fuel Complex, Hyderabad (India)

Description

Zirconium based alloys are the natural choice for both fuel element and in-core structural components in the water cooled thermal reactors, namely BWRs, PWRs and PHWRs. Nuclear Fuel Complex (NFC), Hyderabad is engaged in the production of zirconium based alloys that are used as hardware in the nuclear industry. After hot working of zircaloy, due to its reactivity, an oxide layer is formed on its surfaces. Hence to remove this oxide layer grit blasting operation using alumina grit sand is followed during which the particles of the sand gets fragmented and the oxide layer on the material thus gets dislodged. Thus alumina grit plays a prominent role in the zircaloy fabrication process. In order to have an ideal and effective removal of the oxide layer from the zircaloy surface, knowledge about the composition of the grit with respect to Al2O3, SiO2, TiO2, Fe2O3, CaO and MgO is essential. Therefore the chemical compositional analysis of alumina grit for confirming to specification becomes an essential step in the Quality Assurance (QA) programme for acceptance of the material. The present paper describes the analytical methodology followed in our laboratory for the chemical analysis of alumina grit samples used in the grit blasting operations

Part of:
Fourth international symposium on nuclear analytical chemistry: book of abstracts

Additional details

Publishing Information

Publisher
Bhabha Atomic Research Centre
Imprint Place
Mumbai (India)
Imprint Title
Fourth international symposium on nuclear analytical chemistry: book of abstracts
Imprint Pagination
366 p.
Journal Page Range
p. 314

Conference

Title
4. international symposium on nuclear analytical chemistry
Acronym
NAC-4
Dates
15-19 Nov 2010
Place
Mumbai (India)

INIS

Country of Publication
India
Country of Input or Organization
India
INIS RN
42067084
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
FUEL ELEMENTS; PHWR TYPE REACTORS; QUALITY ASSURANCE; REACTOR CORES; ZIRCALOY
Descriptors DEC
ALLOYS; HEAVY WATER COOLED REACTORS; HEAVY WATER MODERATED REACTORS; REACTOR COMPONENTS; REACTORS; TRANSITION ELEMENT ALLOYS; ZIRCONIUM ALLOYS; ZIRCONIUM BASE ALLOYS

Optional Information

Notes
5 refs.