A practical cesium axial migration model for fast reactor fuel pins

IF 2.6 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY
Fabien Bernachy-Barbe, Tommaso Barani, Jean-Christophe Dumas, Alexandre Kallen
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引用次数: 0

Abstract

Cesium is a volatile fission product which plays a major role in the formation of gap-filling compounds and in the internal cladding corrosion in Fast Breeder Reactor fuel pins operating at elevated temperatures and high burnup. In order to compute reliably the physical and chemical state of the gap, accurate fission product inventories are required. However, volatile species are known to significantly migrate down the radial and axial thermal gradients upon release from the fuel. In the present work, a pragmatic axial diffusion model for cesium is proposed, based on the proven concept of saturation concentration, and an empirical law for computing the vapor pressure of cesium at equilibrium with MOX fuel. This approach is shown to be predictive of the axial distribution of cesium measured through gamma spectrometry for a large database of fuels. Cesium accumulations, which are highly sensitive to local thermal gradients, are satisfactorily reproduced, contributing to the validation of the PLEIADES/GERMINAL V3 fuel performance code multiphysics coupling.
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来源期刊
Nuclear Engineering and Technology
Nuclear Engineering and Technology 工程技术-核科学技术
CiteScore
4.80
自引率
7.40%
发文量
431
审稿时长
3.5 months
期刊介绍: Nuclear Engineering and Technology (NET), an international journal of the Korean Nuclear Society (KNS), publishes peer-reviewed papers on original research, ideas and developments in all areas of the field of nuclear science and technology. NET bimonthly publishes original articles, reviews, and technical notes. The journal is listed in the Science Citation Index Expanded (SCIE) of Thomson Reuters. NET covers all fields for peaceful utilization of nuclear energy and radiation as follows: 1) Reactor Physics 2) Thermal Hydraulics 3) Nuclear Safety 4) Nuclear I&C 5) Nuclear Physics, Fusion, and Laser Technology 6) Nuclear Fuel Cycle and Radioactive Waste Management 7) Nuclear Fuel and Reactor Materials 8) Radiation Application 9) Radiation Protection 10) Nuclear Structural Analysis and Plant Management & Maintenance 11) Nuclear Policy, Economics, and Human Resource Development
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