Leaching of 53 MW/d kg U spent nuclear fuel in a flow-through reactor-Reference-Cited by-同舟云学术

Leaching of 53 MW/d kg U spent nuclear fuel in a flow-through reactor

Published:2009-01 Issue:9 Volume:97 Page:
ISSN:0033-8230
Container-title:Radiochimica Acta
language:
Short-container-title:

Author:

Serrano-Purroy Daniel,Clarens Frederic,Glatz Jean-Paul,Wegen Detlef,Christiansen Birgit,de Pablo Joan,Giménez Javier,Casas Ignasi,Martinez-Esparza Aurora

Publisher

Walter de Gruyter GmbH

Subject

Physical and Theoretical Chemistry

Link

https://www.degruyter.com/document/doi/10.1524/ract.2009.1640/pdf

Reference29 articles.

1. Fuel corrosion processes under waste disposal conditions

2. Spent Nuclear Fuel

3. Determination of dissolution rates of spent fuel in carbonate solutions under different redox conditions with a flow-through experiment

4. UO2. Matrix Dissolution Rates and Grain Boundary Inventories of Cs, Sr, and Tc in Spent Lwr Fuel

5. Parametric study of LWR spent fuel dissolution kinetics

Cited by 9 articles. 订阅此论文施引文献订阅此论文施引文献，注册后可以免费订阅5篇论文的施引文献，订阅后可以查看论文全部施引文献

1. Release of Cs, Sr and Rb from two high–burnup spent nuclear fuels: Effect of the dishing and the internal grain boundaries;Journal of Nuclear Materials;2024-09

2. Fast release from clad and declad spent UOX PWR fuel segments in a bicarbonate solution under anoxic conditions;Journal of Nuclear Materials;2021-12

3. Contribution of phases segregated from the UO2 matrix to the release of radionuclides from spent nuclear fuel and duration of the Instant Release Fraction (IRF);Journal of Nuclear Materials;2020-04

4. Retention of cesium and strontium by uranophane, Ca(UO2)2(SiO3OH)2·5H2O;Journal of Hazardous Materials;2018-07

5. Instant release fraction corrosion studies of commercial UO 2 BWR spent nuclear fuel;Journal of Nuclear Materials;2017-05