The application of martensitic stainless steels in long lifetime fusion first wall/blankets

Rosenwasser, S.N.; Miller, P.H.; Dalessandro, J.A.; Rawls, J.M.; Toffolo, W.; Chen, W.

doi:10.1016/0022-3115(79)90487-2

Cited by 61 publications

(13 citation statements)

References 1 publication

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“…Sandvik HT9 was the first ferritic/martensitic steel considered in the US Fusion Materials Program when it was decided to investigate these steels as structural materials for the first wall and blanket structures of fusion reactors [6,7]. Similarly, the first such steels in the programs in Europe and Japan were the steels previously considered in their fast reactor programs (i.e., EM-12, FV448, DIN 1.4914, and JFMS) [6,8].…”

Section: Fusion Reactor Studiesmentioning

confidence: 99%

Ferritic/martensitic steels for next-generation reactors

Klueh

Nelson

2007

Journal of Nuclear Materials

758

255

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Section: Fusion Reactor Studiesmentioning

confidence: 99%

Ferritic/martensitic steels for next-generation reactors

Klueh

Nelson

2007

Journal of Nuclear Materials

758

255

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“…In FIRD ferritic/martensitic steels developed in the European Union, Japan, and the United States, molybdenum was replaced by tungsten in the conventional Cr-Mo steels to produce Cr-W steels; niobium was replaced by tantalum. [4,5,6] Just as the work on conventional steels emphasized the high-chromium steels 9Cr-1MoVNb and 12Cr-1MoVW, [1,2,3] work on reduced-activation steels has concentrated on 7 to 10 pct Cr steels. [4,5,6] Initial studies at Oak Ridge National Laboratory (ORNL) were on steels with 2.25 to 12 pct Cr.…”

Section: Introductionmentioning

confidence: 99%

“…The first steels considered in the U.S. Fusion Reactor Materials Program were Sandvik HT9 (nominally Fe-12Cr-1Mo-0.25V-0.5W-0.5Ni-0.2C, here designated 12Cr-1MoVW); [1] modified 9Cr-1Mo (nominally Fe-9Cr-1Mo-0.2V-0.06Nb-0.1C, designated 9Cr-1MoVNb); [2] and 2.25Cr-1Mo (Fe-2.25Cr-1Mo-0.1C). [3] All compositions are in weight percent.…”

Section: Introductionmentioning

confidence: 99%

Bainitic chromium-tungsten steels with 3 Pct chromium

Klueh

Alexander

Maziasz

1997

Metall Mater Trans A

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Previous work on 3Cr-1.5MoV (nominally Fe-3Cr-2.5Mo-0.25V-0.1C), 2.25Cr-2W (Fe-2.25Cr-2W-0.1C), and 2.25Cr-2WV (Fe-2.25Cr-2W-0.25V-0.1C) steels indicated that the impact toughness of these steels depended on the microstructure of the bainite formed during continuous cooling from the austenitization temperature. Microstructures formed during continuous cooling can differ from classical upper and lower bainite formed during isothermal transformation. Two types of nonclassical microstructures were observed depending on the cooling rate: carbide-free acicular bainite at rapid cooling rates and granular bainite at slower cooling rates. The Charpy impact toughness of the acicular ferrite was considerably better than for the granular bainite. It was postulated that alloying to improve the hardenability of the steel would promote the formation of acicular bainite, just as increasing the cooling rate does. To test this, chromium and tungsten were added to the 2.25Cr-2W and 2.25Cr-2WV steel compositions to increase their hardenability. Charpy testing indicated that the new 3Cr-W and 3Cr-WV steels had improved impact toughness, as demonstrated by lower ductilebrittle transition temperatures and higher upper-shelf energies. This improvement occurred with less tempering than was necessary to achieve similar toughness for the 2.25Cr steels and for high-chromium (9 to 12 pct Cr) Cr-W and Cr-Mo steels.

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“…The low-activation ferritic-martensitic steels are candidate materials for the first wall and blanket of fusion reactors due to their lower shift of the ductileto-brittle transition temperature after neutron irradiation as compared to conventional ferritic-martensitic steels [1,2].…”

Section: Introductionmentioning

confidence: 99%