Irradiation experiments on high temperature gas-cooled reactor fuels and graphites at the high flux reactor petten-Reference-Cited by-同舟云学术

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Irradiation experiments on high temperature gas-cooled reactor fuels and graphites at the high flux reactor petten

Published:1990-04 Issue:1 Volume:171 Page:31-36
ISSN:0022-3115
Container-title:Journal of Nuclear Materials
language:en
Short-container-title:Journal of Nuclear Materials

Author:

Ahlf J.,Conrad R.,Cundy M.,Scheurer H.

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering,General Materials Science,Nuclear and High Energy Physics

Reference11 articles.

1. Spherical fuel elements for advanced HTR manufacture and qualification by irradiation testing;Mehner;J. Nucl. Mater.,1990

2. High Flux Materials Testing Reactor, HFR Petten, Characteristics of Facilities and Standard Irradiation Devices;Röttger;EUR 5700EN,1986

3. Bestrahlungs-erprobung und Auswertung von Daten für HTR-LEU Referenzbrennelemente im HFR Petten;Conrad,1983

4. Long-term Testing of HTR Fuel Elements in the Federal Republic of Germany;Nickel;KFA report, Jül-Spez-383,1986

5. Proc. Statusseminar Hochtemperaturreaktor-Brennstoffkreislauf;Pott,1987

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1. Graphite and Carbon Fiber Composite for Fusion;Comprehensive Nuclear Materials;2020

2. Scaling analysis for the direct reactor auxiliary cooling system for FHRs;Nuclear Engineering and Design;2015-04

3. New experimental device for VHTR structural material testing and helium coolant chemistry investigation – High Temperature Helium Loop in NRI Řež;Nuclear Engineering and Design;2012-10

4. Results of the HFR-EU1 fuel irradiation of INET and AVR pebbles in the HFR Petten;Nuclear Engineering and Design;2012-10

5. Carbon as a Fusion Plasma-Facing Material;Comprehensive Nuclear Materials;2012

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