Accident testing of high-temperature reactor fuel elements from the HFR-EU1bis irradiation-Reference-Cited by-同舟云学术

Accident testing of high-temperature reactor fuel elements from the HFR-EU1bis irradiation

Published:2011-08 Issue:8 Volume:241 Page:2813-2821
ISSN:0029-5493
Container-title:Nuclear Engineering and Design
language:en
Short-container-title:Nuclear Engineering and Design

Author:

Freis D.,Bottomley P.D.W.,Kellerbauer A.I.,Rondinella V.V.,Van Uffelen P.

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. Modelling of the HFR-EU1bis experiment and thermomechanical evaluation;de Groot;Nucl. Eng. Des.,2008

2. de Groot, S., Fütterer, M.A., Knol, S., 2010. The limit of AVR fuel? behaviour of metallic fission products in HFR-EU1bis. In: 5th International Topical Meeting on High Temperature Reactor Technology, Prague, Czech Republic, p. 189, unpublished.

3. Fission-product behaviour during irradiation of TRISO-coated particles in the HFREU1bis experiment;de Groot,2008

4. Duwe, R., Kühnlein, W., 1975. Berechnung des Spaltproduktinventars in Brennelementen mit U-235, Th-232 und U-238 als Schwermetalleinsatz. Internal Report FZJ-IRW-IB 11/75, Research Center Jülich, Germany.

5. Postirradiation testing of high temperature reactor spherical fuel elements under accident conditions;Freis;J. Eng. Gas Turb. Power,2010

Cited by 10 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. Burn-up determination and accident testing of HTR-PM fuel elements irradiated in the HFR Petten;Nuclear Engineering and Design;2020-02

2. TRISO-Coated Particle Fuel Fabrication and Performance;Comprehensive Nuclear Materials;2020

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

4. Key results from irradiation and post-irradiation examination of AGR-1 UCO TRISO fuel;Nuclear Engineering and Design;2018-04

5. KüFA safety testing of HTR fuel pebbles irradiated in the High Flux Reactor in Petten;Nuclear Engineering and Design;2016-09