Impurity effects on reduced-activation ferritic steels developed for fusion applications

Klueh, R.L.; Cheng, E.T.; Grossbeck, M.L.; Bloom, E.E.

doi:10.1016/s0022-3115(00)00060-x

Cited by 72 publications

(40 citation statements)

References 7 publications

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“…An essential task for the U.S. materials community will be to provide further irradiation data, well before the start of construction of any FNSF, to confirm that the first generation (GEN-I) reduced-activation ferritic/martensitic (RAFM) alloys (such as the Japanese steel (F82H) and European steel (EUROFER)) [15] could survive at least 20 dpa at the first wall (FW). This confirmation could possibly be derived from irradiation experiments utilizing the spallation neutron source (SNS) experiment [16], the High Flux Isotope Reactor (HFIR) [17], and heavy ion facilities to partially simulate the fusion irradiation environment.…”

Section: Mtm and Main Attributesmentioning

confidence: 99%

TBM/MTM for HTS-FNSF: An Innovative Testing Strategy to Qualify/Validate Fusion Technologies for U.S. DEMO

et al. 2016

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Abstract:The qualification and validation of nuclear technologies are daunting tasks for fusion demonstration (DEMO) and power plants. This is particularly true for advanced designs that involve harsh radiation environment with 14 MeV neutrons and high-temperature operating regimes. This paper outlines the unique qualification and validation processes developed in the U.S., offering the only access to the complete fusion environment, focusing on the most prominent U.S. blanket concept (the dual cooled PbLi (DCLL)) along with testing new generations of structural and functional materials in dedicated test modules. The venue for such activities is the proposed Fusion Nuclear Science Facility (FNSF), which is viewed as an essential element of the U.S. fusion roadmap. A staged blanket testing strategy has been developed to test and enhance the DCLL blanket performance during each phase of FNSF D-T operation. A materials testing module (MTM) is critically important to include in the FNSF as well to test a broad range of specimens of future, more advanced generations of materials in a relevant fusion environment. The most important attributes for MTM are the relevant He/dpa ratio (10-15) and the much larger specimen volumes compared to the 10-500 mL range available in the International Fusion Materials Irradiation Facility (IFMIF) and European DEMO-Oriented Neutron Source (DONES).

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Section: Mtm and Main Attributesmentioning

confidence: 99%

TBM/MTM for HTS-FNSF: An Innovative Testing Strategy to Qualify/Validate Fusion Technologies for U.S. DEMO

et al. 2016

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“…The eventual target of alloy development in terms of property levels is defined in the published work in this area Klueh et al 2000Baluc et al 2007a). In most papers, the target mechanical properties were expected to be comparable or better than 9Cr-1Mo tempered martensitic steels and the target for induced activity level was indicated.…”

Section: Performance Targetmentioning

confidence: 99%

9-12Cr Heat-Resistant Steels

Yan

Wang

Shan³

et al. 2015

Engineering Materials

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“…Regarding commercial ferritic/martensitic steels, we investigate the activation of HT9 and mod.9Cr-1Mo (T91), steels considered for different nuclear -fusion and fast reactors-applications 7,8 . Sandvik HT9, nominal 12Cr-1Mo-0.3V-0.5W-0.5Ni-0.2C was used for the IFE LIBRA reactor concept.…”

Section: Iia Candidate Materials: Commercial and Reduced Activationmentioning

confidence: 99%

“…2 The composition of T91 ferritic steel, nominal 9Cr-1Mo-0.2V-0.07Nb-0.06N-0.1C, is taken from Ref. 7.…”

Section: Iia Candidate Materials: Commercial and Reduced Activationmentioning

confidence: 99%

“…Steels, which are widely used in power plants and other industries under demanding operational requirements, have been considered from the beginnings of fusion technology as one of the most promising candidate structural materials for inertial and magnetic fusion energy (IFE and MFE) reactor chambers. [2][3][4][5][6][7][8][9][10][11][12][13] As continuation of the ARIES-IFE study 12 , an extensive activation analysis in selecting steels for the HYLIFE-II chamber qualifying for successful waste management was performed 13 . Different commercial austenitic and Cr-Mo ferritic/martensitic steels, as well as some MFE-intended reduced-activation steels were studied.…”

Section: Introductionmentioning

confidence: 99%

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