Effect of compaction pressure on the thermal conductivity of UO2 BeO Gd2O3 pellets
- 1. Centro de Desenvolvimento da Tecnologia Nuclear (CDTN/CNEN-MG), Belo Horizonte, MG (Brazil)
Description
The (U,Gd)O2 fuels are used in pressurized water reactors (PWR) to control the neutron population in the reactor during the early life with the purpose of extended fuel cycles and higher target burnups. Nevertheless, the incorporation of Gd2O3 in the UO2 fuel decreases the thermal conductivity, leading to premature fuel degradation. This is the reason for the addition of beryllium oxide (BeO) which has a high thermal conductivity and is chemically compatible with UO2. Pellets with BeO contents of 2 and 3 wt% and 6wt% of Gd2O3 solid solution were compacted at pressures of 400 MPa, 500 MPa, 600 MPa and 700 MPa based on the conventional UO2 pellet manufacturing process with steps of the mixing of powders, pressing, and sintering under reducing atmosphere. The purpose of this study was investigate the effect of BeO, Gd2O3 and compaction pressure on the thermal conductivity of the UO2 pellets. The thermal diffusivity and conductivity of the pellets were determined from 298 K to 773 K and the results obtained were compared to fuel pellets of UO2. The thermal diffusivity was determined by Laser Flash and Thermal Quadrupole methods and the thermal conductivity was calculated from the product of thermal diffusivity, the specific heat capacity and density. The sintered density of the pellets was determined by xylol penetration and immersion method. The results showed an increase in the thermal conductivity of the pellets with additions of BeO and with the increase of the compaction pressure as compared to the values obtained with UO2 pellets. (author)
Additional details
Publishing Information
- Publisher
- ABEN
- Imprint Place
- Rio de Janeiro, RJ (Brazil)
- ISBN
- 978-85-99141-08-3
- Imprint Title
- Proceedings of the INAC 2019: international nuclear atlantic conference. Nuclear new horizons: fueling our future
- Imprint Pagination
- 6019 p.
- Journal Page Range
- p. 5079-5087
Conference
- Title
- international nuclear atlantic conference; 21. meeting on nuclear reactor physics and thermal hydraulics - ENFIR; 14. meeting on nuclear applications - ENAN; 6. meeting on nuclear industry - ENIN; 1. international workshop on thorium - ITHOR-WS
- Acronym
- INAC 2019
- Dates
- 21-25 Oct 2019
- Place
- Santos, SP (Brazil)
INIS
- Country of Publication
- Brazil
- Country of Input or Organization
- Brazil
- INIS RN
- 51010431
- Subject category
- S11: NUCLEAR FUEL CYCLE AND FUEL MATERIALS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BERYLLIUM OXIDES; DENSITY; FUEL PELLETS; GADOLINIUM OXIDES; NUCLEAR FUELS; PRESSURE DEPENDENCE; SINTERING; SPECIFIC HEAT; THERMAL CONDUCTIVITY; THERMAL DIFFUSIVITY; URANIUM DIOXIDE
- Descriptors DEC
- ACTINIDE COMPOUNDS; ALKALINE EARTH METAL COMPOUNDS; BERYLLIUM COMPOUNDS; CHALCOGENIDES; ENERGY SOURCES; FABRICATION; FUELS; GADOLINIUM COMPOUNDS; MATERIALS; OXIDES; OXYGEN COMPOUNDS; PELLETS; PHYSICAL PROPERTIES; RARE EARTH COMPOUNDS; REACTOR MATERIALS; THERMODYNAMIC PROPERTIES; URANIUM COMPOUNDS; URANIUM OXIDES
Optional Information
- Notes
- R05-029