Probabilistic safety analysis performing a RAMI study of the Tritium extraction system for the ITER HCPB test blanket module

Autor: Borràs Farnós, Jordà

This project arises from an awarded contract to IDOM. The primary goal of this undertaking is to assess the reliability and availability of the Tritium Extraction System (TES) within the ITER Test Blanket Module (TBM) Ancillary Systems. The introduct

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=od______3484::4d2630bf027d92891eab3e94a0246712
https://hdl.handle.net/2117/388433

Implementation, review and monitoring of the safety parameters of 9 leak detection systems for the ITER nuclear fusion plant

Autor: Prat Baucells, Jordi

Publikováno v: UPCommons. Portal del coneixement obert de la UPC
Universitat Politècnica de Catalunya (UPC)

Description: inside the framework of the project for the design and supply of nine leak detection systems for the Vacuum vessel, the Neutral Beam and the cryostat of the ITER facility, the following tasks will be performed: - Revision of the nuclear

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=dedup_wf_001::ed02d6d033e8f251862a1455aa03de60
http://hdl.handle.net/2117/368678

A CFD Benchmark on the Thermal Hydraulic Behavior of ITER’s Vacuum Vessel

Autor: Catalán Conde, David

Publikováno v: UPCommons. Portal del coneixement obert de la UPC
Universitat Politècnica de Catalunya (UPC)

The current project presents a CFD Benchmark on the Thermal-Hydraulic (TH) performance of ITER’s Vacuum Vessel. The geometry has been selected to be of one of the 4 Poloidal Segments (PS), the PS#01, of a Regular Sector (RS) 5, RS#05. A commercial

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=dedup_wf_001::9147a00c7ac5f4336db510842d3c7e4f
https://hdl.handle.net/2117/332811

Hacia la monitorización dinámica del inventario de tritio en los sistemas auxiliares de un reactor de fusión

Autor: Batet Miracle, Lluís|||0000-0003-1882-6313, Iraola de Acevedo, Eduardo, Sedano Miguel, Luis Ángel|||0000-0002-3629-8297, Nougués, José María

Publikováno v: UPCommons. Portal del coneixement obert de la UPC
Universitat Politècnica de Catalunya (UPC)

La sostenibilidad de la fusión nuclear depende, entre otros condicionantes, de la capacidad de regeneración de tritio. Los requisitos de protección radiológica imponen severas limitaciones a las emisiones ambientales de tritio, lo que a su vez ob

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=dedup_wf_001::a9c7ac8835df95969e444235d19b428d
https://hdl.handle.net/2117/178595

Numerical analysis of the manufacturing processes of a mock-up of the ITER NHF First Wall Panel

Autor: Miguel Cervera, Michele Chiumenti, C. Agelet de Saracibar, J.M. González, F. Samaniego, I. Cobo

Publikováno v: UPCommons. Portal del coneixement obert de la UPC
Universitat Politècnica de Catalunya (UPC)
Recercat. Dipósit de la Recerca de Catalunya
instname
Scipedia Open Access
Scipedia SL

The objective of ITER is to build a new Tokamak, with the goal of demonstrating the scientific and technical feasibility of fusion power. The First Wall Panels are the inner component of the reactor, built with different materials that must support h

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_dedup___::56a3e140fcd26eed26ba84bd85329016
https://www.researchgate.net/publication/326423272_Numerical_analysis_of_the_manufacturing_processes_of_a_mock-up_of_the_ITER_NHF_First_Wall_Panel