Fission gas release measurements in mixed carbide and mixed oxide fuel pins
Creators
- 1. Material and Metallurgy Group, Indira Gandhi Centre for Atomic Research, Kalpakkam (India)
Description
Fission Gas Release (FGR) and fuel swelling are two important facets of fuel performance. Release of fission gases results in degradation in heat transfer due to bond gas dilution and enhanced stress in the clad due to internal pressure, whereas, retention of fission gases in the fuel matrix causes swelling leading to the Fuel Clad Mechanical Interaction (FCMI). Hence estimation of FGR is important to evaluate the fuel performance. As a part of Post Irradiation Examination (PIE), FGR measurements has been carried out on Plutonium-rich mixed carbide fuel pins (U0.3Pu0.7)C of FBTR fuel sub-assembly (FSA) discharged at various burnup levels and on the fuel pins from a failed carbide sub-assembly. FGR measurements have also been carried out on the fuel pins of MOX test sub-assembly after a burn-up of 112 GWd/t. This paper discusses the results of gas release measurements in these fuel pins
Additional details
Publishing Information
- Publisher
- Indira Gandhi Centre for Atomic Research
- Imprint Place
- Kalpakkam (India)
- Imprint Title
- Proceedings of the DAE-BRNS theme meeting commemorating seventy five years of the discovery of Plutonium 239
- Imprint Pagination
- 230 p.
- Journal Page Range
- 3 p.
Conference
- Title
- DAE-BRNS theme meeting commemorating seventy five years of the discovery of Plutonium 239
- Acronym
- Plutonium 75
- Dates
- 23-25 May 2016
- Place
- Kalpakkam (India)
INIS
- Country of Publication
- India
- Country of Input or Organization
- India
- INIS RN
- 48005174
- Subject category
- S11: NUCLEAR FUEL CYCLE AND FUEL MATERIALS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BURNUP; FISSION PRODUCT RELEASE; FUEL PINS; FUEL-CLADDING INTERACTIONS; MIXED CARBIDE FUELS; MIXED OXIDE FUELS; POST-IRRADIATION EXAMINATION
- Descriptors DEC
- ENERGY SOURCES; FUEL ELEMENTS; FUELS; MATERIALS; NUCLEAR FUELS; REACTOR COMPONENTS; REACTOR MATERIALS; SOLID FUELS
Optional Information
- Notes
- 1 ref., 2 figs., 1 tab.