Irradiation devices and irradiation programmes at the high flux reactor (HFR) Petten for the investigation of the irradiation behaviour of stainless steels

Author:

Markgraf J.F.W.,Tartaglia G.P.,Tsotridis G.

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

Reference22 articles.

1. High flux reactor (HFR) Petten, characteristics of the installation and the irradiation facilities,1993

2. HFR irradiation testing of fusion materials;Conrad;CEC-Rep. EUR 9515 EN,1984

3. Effects of temperature and strain rate on the low cycle fatigue properties of neutron irradiated stainless steel 1.4948;de Vries;ASTM STP 782,1982

4. Fatigue crack growth in neutron irradiated type 304 and 316 stainless steels;de Vries;ASTM STP 870,1985

5. J-integral toughness of low fluence neutron irradiated stainless steel DIN 1.4948;de Vries;ASTM STP 956,1987

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. In-reactor Creep Testing: Techniques;Reference Module in Materials Science and Materials Engineering;2016

2. Irradiation simulation techniques for the study of reactor pressure vessel (RPV) embrittlement;Irradiation Embrittlement of Reactor Pressure Vessels (RPVs) in Nuclear Power Plants;2015

3. In-reactor Creep Testing: Techniques;Encyclopedia of Materials: Science and Technology;2001

4. LYRA and other projects on RPV steel embrittlement;Nuclear Engineering and Design;2000-02

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