Published 2018 | Version v1
Book

Overview of non-destructive tests on mixed oxide fuel pins

  • 1. Advanced Fuel Fabrication Facility, Nuclear Recycle Board, Bhabha Atomic Research Centre, Tarapur-401502 (India)

Description

The (U,Pu)O2, Mixed Oxide (MOX) fuel pellets are fabricated by conventional powder metallurgical route involving steps like mixing, milling, pre-compaction, granulation and final compaction followed by sintering. The stack of fuel pellets is loaded in bottom end plug welded clad tubes. The tubes are sealed by end plugs using GTAW welding procedure. Various non-destructive tests are carried out on finished MOX fuel pins like X-ray radiography, Helium leak testing and X-ray Gamma Autoradiography (X-GAR). X-ray radiography is carried out to check the physical integrity of end plug welds. Helium leak testing is carried out to eliminate the possibilities of existence of leak in the fuel pins. X-GAR technique is used to check internal hardware components and cross mixing of DDUO2, pellets in stack of MOX and vice-versa

Part of:
Proceedings of the second DAE-BRNS symposium on recent advances in nuclear fuel cycle activities

Additional details

Publishing Information

Publisher
Indian Association of Nuclear Chemists and Allied Scientists
Imprint Place
Tarapur (India)
Imprint Title
Proceedings of the second DAE-BRNS symposium on recent advances in nuclear fuel cycle activities
Imprint Pagination
178 p.
Journal Page Range
p. 134-135

Conference

Title
2. DAE-BRNS symposium on recent advances in nuclear fuel cycle activities
Acronym
NUFUC-2018
Dates
26-27 Oct 2018
Place
Tarapur (India)

Optional Information