{rfName}
NE

Indexed in

Altmetrics

Analysis of institutional authors

Sanz, JAuthorOgando, FAuthor

Share

October 3, 2022
Publications
>
Proceedings Paper
No

NEUTRONIC ASSESSMENT OF CANDIDATE MATERIALS FOR TF COILS SHIELDING IN A DEMO FUSION REACTOR BASED ON A DCLL BLANKET

Publicated to: Fusion Science And Technology. 62 (1): 190-195 - 2012-07-01 62(1), DOI: 10.13182/FST11-425

Authors:

Catalan, J. P.; Sanz, J.; Ogando, F.; Pampin, R.;
[+]

Affiliations

Culham Ctr Fus Energy, Culham Sci Ctr, Abingdon, Oxon, England - Author
UNED, Dept Energy Engn, Madrid 28040, Spain - Author

Abstract

Under the Spanish Breeding Blanket Technology Program TECNO_FUS, a conceptual design of a dual-coolant lithium-lead (DCLL) blanket for DEMO is being revisited. In this work, different shielding candidate materials are assessed in their ability to satisfy the radiation load requirements that must be fulfilled in the toroidal field (TF) coils: absorbed dose in the insulator (Epoxy), peak fast neutron fluence in the superconductor (Nb(3)Siz), peak nuclear heating in the winding pack and maximum neutron fluence in the cooper stabilizer. Furthermore, the impact of the material choice on waste management requirements of both shielding and vacuum vessel (VV) materials is evaluated, and the performance of candidate materials is examined in terms of the helium production in the VV SS316LN material and its implications in re-weldability. Materials discussed for the High Temperature Shield are Eurofer, graphite, B4C, WC and WB4C, while the metal hydrides ZrH2, Zr(BH4)(4), and TiH2 are discussed for the Low Temperature Shield. In the case of DEMO irradiation scenario, all the analyzed material combinations fulfill the design requirements for the waste management of the shield and VV, He production in the VV wall and TF coils radiation loads requirements.
[+]

Keywords

Absorbed doseBorohydrideBreeding blanketsCandidate materialsConceptual designCoolantsDcll blanketDemoDesign requirementsDual-coolant lithium-leadEuroferFast neutron fluenceFusion reactorsHeliumHelium productionHigh temperatureHydrideHydridesIterLithiumLithium-leadLow temperaturesMaterial choiceMaterial combinationMaterialsMetal hydridesNeutron fluencesNeutron irradiationNeutronicsNuclear heatingRadiation loadRadiation shieldingReactor shieldingShieldingSolid breeder blanketSuperconducting coilsTechnology programsTemperatureTf coilsToroidal field coilsVacuum applicationsVacuum vesselWaste managementWinding packsZirconium

Quality index

Bibliometric impact. Analysis of the contribution and dissemination channel

The work has been published in the journal Fusion Science And Technology due to its progression and the good impact it has achieved in recent years, according to the agency Scopus (SJR), it has become a reference in its field. In the year of publication of the work, 2012, it was in position , thus managing to position itself as a Q2 (Segundo Cuartil), in the category Civil and Structural Engineering. Notably, the journal is positioned en el Cuartil Q3 for the agency WoS (JCR) in the category Nuclear Science & Technology.

Independientemente del impacto esperado determinado por el canal de difusión, es importante destacar el impacto real observado de la propia aportación.

Según las diferentes agencias de indexación, el número de citas acumuladas por esta publicación hasta la fecha 2025-12-21:

  • WoS: 3
  • Scopus: 4
[+]

Impact and social visibility

From the perspective of influence or social adoption, and based on metrics associated with mentions and interactions provided by agencies specializing in calculating the so-called "Alternative or Social Metrics," we can highlight as of 2025-12-21:

  • The use of this contribution in bookmarks, code forks, additions to favorite lists for recurrent reading, as well as general views, indicates that someone is using the publication as a basis for their current work. This may be a notable indicator of future more formal and academic citations. This claim is supported by the result of the "Capture" indicator, which yields a total of: 8 (PlumX).
[+]

Leadership analysis of institutional authors

This work has been carried out with international collaboration, specifically with researchers from: United Kingdom.

[+]