Materials needs for fusion, Generation IV fission reactors and spallation neutron sources – similarities and differences

Mansur, L.K.; Rowcliffe, A.F.; Nanstad, R.K.; Zinkle, S.J.; Corwin, W.R.; Stoller, R.E.

doi:10.1016/j.jnucmat.2004.04.016

Cited by 273 publications

(113 citation statements)

References 17 publications

(15 reference statements)

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“…These challenges are faced by the production of advanced material with unique performances [74][75][76][77][78], these material include ferritic/martensitic steels, V-Cr-Ti alloys and SiC/SiC ceramic composites.…”

Section: Austenitic and Ferritic/martensitic Steels And Other Advancementioning

confidence: 99%

“…This figure is taken from [18]. Table 3 is it possible read also the main operating parameters of these three types of plants [78]." Figure 3.…”

Section: Austenitic and Ferritic/martensitic Steels And Other Advancementioning

confidence: 99%

“…"There is an overlap between the temperatures of fusion, fission and spallation facilities as showed in Figure 2" taken from [78].…”

Section: "Inmentioning

confidence: 99%

“…Summary of operating parameters for fusion, fission and spallation facilities. This table is taken from [78].…”

Section: "Inmentioning

confidence: 99%

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A Review of Dangerous Dust in Fusion Reactors: from Its Creation to Its Resuspension in Case of LOCA and LOVA

et al. 2016

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Abstract:The choice of materials for the future nuclear fusion reactors is a crucial issue. In the fusion reactors, the combination of very high temperatures, high radiation levels, intense production of transmuting elements and high thermomechanical loads requires very high-performance materials. Erosion of PFCs (Plasma Facing Components) determines their lifetime and generates a source of impurities (i.e., in-vessel tritium and dust inventories), which cool down and dilute the plasma. The resuspension of dust could be a consequences of LOss of Coolant Accidents (LOCA) and LOss of Vacuum Accidents (LOVA) and it can be dangerous because of dust radioactivity, toxicity, and capable of causing an explosion. These characteristics can jeopardize the plant safety and pose a serious threat to the operators. The purpose of this work is to determine the experimental and numerical steeps to develop a numerical model to predict the dust resuspension consequences in case of accidents through a comparison between the experimental results taken from campaigns carried out with STARDUST-U and the numerical simulation developed with CFD codes. The authors in this work will analyze the candidate materials for the future nuclear plants and the consequences of the resuspension of its dust in case of accidents through the experience with STARDUST-U.

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Section: Austenitic and Ferritic/martensitic Steels And Other Advancementioning

confidence: 99%

“…This figure is taken from [18]. Table 3 is it possible read also the main operating parameters of these three types of plants [78]." Figure 3.…”

Section: Austenitic and Ferritic/martensitic Steels And Other Advancementioning

confidence: 99%

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A Review of Dangerous Dust in Fusion Reactors: from Its Creation to Its Resuspension in Case of LOCA and LOVA

et al. 2016

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“…The motivation for these studies is the fact that high-chromium ferritic/martensitic steels, containing up to 15 at.% of Cr, are candidate materials for advanced fi ssion reactors (Generation IV), accelerator-driven systems using spallation neutron sources and fusion reactors [8,9]. These types of steels are capable of performing reliably for a long time under high irradiation levels (total dose of 50 to 200 displacements per atom (dpa)) and at high temperatures (up to 900 K).…”

Section: Introductionmentioning

confidence: 99%

Temperature dependence of the short-range order parameter for Fe_0.90Cr_0.10 and Fe_0.88Cr_0.12 alloys

Idczak

Konieczny

2015

Nukleonika

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Abstract. The 57Fe Mössbauer spectra for the iron-based solid solutions Fe 0.90 Cr 0.10 and Fe 0.88 Cr 0.12 were measured at different temperatures ranging from 300 K to 900 K. Analysis of the obtained spectra shows that the distribution of impurity atoms in the two fi rst coordination shells of 57 Fe nuclei is not random and it cannot be described by the binomial distribution. Quantitatively, the effects were described in terms of the atomic short-range order (SRO) parameters and the pair-wise interaction energy with the help of a quasi-chemical type formulation introduced by Cohen and Fine. The obtained results reveal strong clustering-type correlations in the studied samples (a predominance of Fe-Fe and Cr-Cr bonds). Moreover, the changes in SRO values observed during thermal processing suggest that the distribution of Cr atoms in an -iron matrix is strongly temperature dependent.

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Design Factor Using a SiC/SiC Composites for Core Component of Gas Cooled Fast Reactor. 2: Thermal Stress

Lee

Naganuma

2007

Mechanical Properties and Performance of Engineering Ceramics and Composites III

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Materials needs for fusion, Generation IV fission reactors and spallation neutron sources – similarities and differences

Cited by 273 publications

References 17 publications

A Review of Dangerous Dust in Fusion Reactors: from Its Creation to Its Resuspension in Case of LOCA and LOVA

A Review of Dangerous Dust in Fusion Reactors: from Its Creation to Its Resuspension in Case of LOCA and LOVA

Temperature dependence of the short-range order parameter for Fe_0.90Cr_0.10 and Fe_0.88Cr_0.12 alloys

Design Factor Using a SiC/SiC Composites for Core Component of Gas Cooled Fast Reactor. 2: Thermal Stress

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Materials needs for fusion, Generation IV fission reactors and spallation neutron sources – similarities and differences

Cited by 273 publications

References 17 publications

A Review of Dangerous Dust in Fusion Reactors: from Its Creation to Its Resuspension in Case of LOCA and LOVA

A Review of Dangerous Dust in Fusion Reactors: from Its Creation to Its Resuspension in Case of LOCA and LOVA

Temperature dependence of the short-range order parameter for Fe0.90Cr0.10 and Fe0.88Cr0.12 alloys

Design Factor Using a SiC/SiC Composites for Core Component of Gas Cooled Fast Reactor. 2: Thermal Stress

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Temperature dependence of the short-range order parameter for Fe_0.90Cr_0.10 and Fe_0.88Cr_0.12 alloys