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Irradiation-resistant ferritic and martensitic

Irradiation-resistant ferritic and martensitic steels as core materials for Generation IV nuclear reactors... [Pg.329]

Mononitride UN and UPuN fuel was initially tested in the BR-10 and BOR-60 reactors at 350—1045 W/cm and 4—9% bumup. Both showed good resistance to irradiation and low reaction rates with liquid metal coolants. They are also compatible with ferritic—martensitic steels, eg, EP-823 and EP-450 up to 800°C for 2000 h and 1200-1300°C for 5 h (Filin, 2000). In 2014-2015, hot cell examinations of UPuN fuel rods irradiated in BOR-60 and BN-600. Irradiation experiments on UPuN FAs for BREST and BN have started (Nikitin, 2015). The main design characteristics of the BREST-OD-300 are given in Table 12.7. [Pg.325]

Teysseyre et al. [125] reported that the density of cracks and crack depth for austenitic stainless steels preirradiated up to 7 dpa increased over the unirradiated case in SCW at 400°C. Under the same irradiation and test conditions, ferritic-martensitic alloys were found to be resistant to cracking. [Pg.140]

See other pages where Irradiation-resistant ferritic and martensitic is mentioned: [Pg.290]    [Pg.290]    [Pg.19]    [Pg.363]    [Pg.409]    [Pg.569]    [Pg.575]    [Pg.30]    [Pg.231]    [Pg.7]    [Pg.48]    [Pg.217]    [Pg.12]    [Pg.14]    [Pg.193]    [Pg.193]    [Pg.365]    [Pg.389]    [Pg.450]    [Pg.584]    [Pg.585]   


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Ferritic

Irradiation resistance

Irradiation-resistant ferritic and martensitic steels

Martensitic

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