Review of sintering and densification in nuclear fuels: Physical mechanisms, experimental results, and computational models
- 1. Department of Mechanical and Nuclear Engineering, Penn State University, University Park, PA 16802 (United States)
- 2. Department of Material Science and Engineering, University of Florida, Gainesville, FL 32611 (United States)
- 3. Fuel Modeling and Simulation, Idaho National Laboratory, P.O. Box 1625, Idaho Falls, ID 83415 (United States)
Description
This work is a review of two density changes common in UO2 nuclear fuel: sintering and irradiation-enhanced densification. These density changes must be understood in order to predict fuel behavior, increase fuel lifetime, and design safer and more economical reactor fuels. The physical causes of each dimensional change are summarized. Then a summary is given of published experimental data as well as conclusions that can be drawn from that data. Finally, the most commonly used models for predicting these behaviors are summarized and compared based on the type of model, assumptions in the model, and the physics accounted for in each model. Models are categorized as empirical, semi-empirical, continuous, or microstructural. Commonly used models are presented, summarized, and compared based on the model category, assumptions, and physics that are included in the models. Finally, recommendations are given for future model development.
Availability note (English)
Available from http://dx.doi.org/10.1016/j.jnucmat.2018.03.046Additional details
Identifiers
- DOI
- 10.1016/j.jnucmat.2018.03.046;
- PII
- S002231151731454X;
Publishing Information
- Journal Title
- Journal of Nuclear Materials
- Journal Volume
- 507
- Journal Page Range
- p. 381-395
- ISSN
- 0022-3115
- CODEN
- JNUMAM
INIS
- Country of Publication
- Netherlands
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 49103082
- Subject category
- S36: MATERIALS SCIENCE;
- Resource subtype / Literary indicator
- Numerical Data
- Descriptors DEI
- CHEMICAL POLISHING; EXPERIMENTAL DATA; MATRICES; NUCLEAR FUELS; REVIEWS; SINTERING; URANIUM DIOXIDE
- Descriptors DEC
- ACTINIDE COMPOUNDS; CHALCOGENIDES; DATA; DOCUMENT TYPES; ENERGY SOURCES; FABRICATION; FUELS; INFORMATION; MATERIALS; NUMERICAL DATA; OXIDES; OXYGEN COMPOUNDS; POLISHING; REACTOR MATERIALS; SURFACE FINISHING; URANIUM COMPOUNDS; URANIUM OXIDES
Optional Information
- Copyright
- Copyright (c) 2017 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.