Evaluation of Fuel-Clad Chemical Interaction in PFBR MOX test fuel pins
Creators
- 1. Metallurgy and Materials Group, Indira Gandhi Centre for Atomic Research, Kalpakkam, 603102 (India)
- 2. Homi Bhabha National Institute, Indira Gandhi Centre for Atomic Research, Kalpakkam, 603102 (India)
Description
Fuel Clad Chemical Interaction (FCCI) is one of the life limiting issues in the MOX fuel pins of fast breeder reactors. Clad wastage due to FCCI coupled with stress arising from fission gas pressure and Fuel Clad Mechanical Interaction (FCMI) due to fuel swelling can lead to fuel pin failure. Non-destructive evaluation (NDE) techniques such as Gamma Scanning, Eddy current testing and Neutron Radiography have been successfully used on MOX fuel pins of a test sub-assembly irradiated in Fast Breeder Test Reactor (FBTR) to a burn-up of 112 GW d/t to detect signatures of FCCI. The results obtained by the various NDE techniques have been correlated and verified through metallographic examination on fuel pin cross-sections. The measured clad wastage of 85 μm agrees well with a model developed for MOX fuel with high Pu content. The results of examinations have enabled validation of the model and given confidence to the designer that PFBR MOX fuel can safely attain the target burn-up of 100 GW d/t.
Availability note (English)
Available from http://dx.doi.org/10.1016/j.jnucmat.2018.06.001Additional details
Identifiers
- DOI
- 10.1016/j.jnucmat.2018.06.001;
- PII
- S0022311517318111;
Publishing Information
- Journal Title
- Journal of Nuclear Materials
- Journal Volume
- 509
- Journal Page Range
- p. 94-101
- ISSN
- 0022-3115
- CODEN
- JNUMAM
INIS
- Country of Publication
- Netherlands
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 49103197
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S36: MATERIALS SCIENCE;
- Descriptors DEI
- CROSS SECTIONS; EDDY CURRENT TESTING; EVALUATION; FBR TYPE REACTORS; FISSION PRODUCTS; FUEL CANS; FUEL PINS; INTERACTIONS; MIXED OXIDE FUELS; NEUTRON RADIOGRAPHY
- Descriptors DEC
- BREEDER REACTORS; ELECTROMAGNETIC TESTING; ENERGY SOURCES; EPITHERMAL REACTORS; FAST REACTORS; FUEL ELEMENTS; FUELS; INDUSTRIAL RADIOGRAPHY; ISOTOPES; MATERIALS; MATERIALS TESTING; NONDESTRUCTIVE TESTING; NUCLEAR FUELS; RADIOACTIVE MATERIALS; REACTOR COMPONENTS; REACTOR MATERIALS; REACTORS; SOLID FUELS; TESTING
Optional Information
- Copyright
- Copyright (c) 2017 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.