Computational analysis of modern HTGR fuel performance and fission product release during the HFR-EU1 irradiation experiment-Reference-Cited by-同舟云学术

Computational analysis of modern HTGR fuel performance and fission product release during the HFR-EU1 irradiation experiment

Published:2014-07 Issue: Volume:273 Page:85-97
ISSN:0029-5493
Container-title:Nuclear Engineering and Design
language:en
Short-container-title:Nuclear Engineering and Design

Author:

Verfondern Karl,Xhonneux André,Nabielek Heinz,Allelein Hans-Josef

Publisher

Elsevier BV

Subject

Mechanical Engineering,Waste Management and Disposal,Safety, Risk, Reliability and Quality,General Materials Science,Nuclear Energy and Engineering,Nuclear and High Energy Physics

Reference15 articles.

1. Results of the HFR-EU1 fuel irradiation of INET and AVR pebbles in the HFR Petten;Laurie,2010

2. Preliminary results of the HFR-EU1 fuel irradiation of INET and AVR pebbles in the HFR Petten;Marmier,2008

3. The European ARCHER project proposal: HTR research towards demonstration;Groot,2010

4. JRC's on-line fission gas release monitoring system in the High Flux Reactor Petten;Laurie,2010

5. Testing of HTR UO2 TRISO fuels in AVR and in material test reactors;Kania;J. Nucl. Mater.,2013

Cited by 4 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. The development of TRIAC-BATAN: a triso fuel performance analysis code;Journal of Physics: Conference Series;2019-04

2. Coated particle fuel: Historical perspectives and current progress;Journal of Nuclear Materials;2019-03

3. Electron microscopy study of Pd, Ag, and Cs in carbon areas in the locally corroded SiC layer in a neutron-irradiated TRISO fuel particle;Journal of the European Ceramic Society;2018-09

4. Distribution of fission products palladium, silver, cerium and cesium in the un-corroded areas of the locally corroded SiC layer of a neutron irradiated TRISO fuel particle;Journal of the European Ceramic Society;2017-08