Zobrazeno 1 - 10
of 48
pro vyhledávání: '"Andrea Ciampichetti"'
Autor:
Nicolas Ghirelli, Marco Giammei, Donato Lioce, Walter Van Hove, Daniel Whitted, Andrea Ciampichetti, Marco Tomasello, Sergio Orlandi, Seokho H. Kim, Andrei Petrov, Bin Guo, Lionel Afzali, Moustafa Moteleb
Publikováno v:
Fusion Science and Technology. 75:841-848
The tokamak cooling water system (TCWS) is the primary cooling system of the ITER tokamak machine, providing cooling water to the vacuum vessel and in-vacuum vessel components. In addition, it prov...
A crucial issue for the design of HCLL (Helium Cooled Lead Lithium) Test Blanket Module of ITER and HCLL, WCLL, DCLL Breeder Blanket of DEMO is to efficiently characterise the tritium inventory inside the blanket and the permeation of tritium into th
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::87ba4ff0214767d380366b5aebb15d82
http://hdl.handle.net/11583/2700946
http://hdl.handle.net/11583/2700946
Publikováno v:
Fusion Engineering and Design. 88:2392-2395
The Water Cooled Lithium Lead (WCLL) blanket is based on the eutectic liquid alloy Pb16Li as breeder material and neutron multiplier, and pressurised water as coolant. The liquid breeder flows at few mm/s in the blanket module while the pressurised w
The interaction between heavy liquid metal (HLM) and water is a safety concern for the preliminary designs of lead fast reactor (i.e. LFR) and of subcritical transmutation system prototypes (i.e. XT-ADS). Current pool-type configurations have steam g
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::2ba67c32580b7b29154a6396fc2133e5
http://hdl.handle.net/11568/827159
http://hdl.handle.net/11568/827159
Autor:
C. Moreno, F.S. Nitti, Andrea Ciampichetti, Italo Ricapito, L.A. Sedano, K. Liger, M. Succi, A. Aiello, David Demange
Publikováno v:
Fusion Engineering and Design. 87:620-624
The HCPB (Helium Cooled Pebble Bed) Test Blanket Module (TBM), developed in EU to be tested in ITER, adopts a ceramic containing lithium as breeder material, beryllium as neutron multiplier and helium at 80 bar as primary coolant. In HCPB-TBM the mai
Autor:
F. Desideri, Marco Utili, Pietro Agostini, A. Aiello, K. Liger, Andrea Ciampichetti, Italo Ricapito
Publikováno v:
Fusion Engineering and Design. 87:1342-1346
The knowledge of the tritium transport parameters in lead lithium is fundamental for the design of the HCLL (helium cooled lead lithium) blanket. In fact, the inventory of tritium in fusion reactors blankets and the permeation of tritium into the bla
Publikováno v:
Fusion Science and Technology. 60:1431-1435
The Coolant Purification System (CPS) together with the Tritium Extraction System (TES) and Helium Cooling System (HCS) are the principal auxiliary circuits of HCLL and HCPB TBMs to be tested in IT...
Publikováno v:
Fusion Engineering and Design. 86:1859-1862
The coolant purification system (CPS) together with the tritium extraction system (TES) and helium cooling system (HCS) are the principal auxiliary circuits of helium-cooled-lithiium–lead (HCLL) and helium-cooled-pebble-bed (HCPB) test blanket modu
Publikováno v:
Fusion Science and Technology. 60:1159-1162
Extraction of tritium from liquid lead lithium eutectic alloy is a key topic for the feasibility of any PbLi based tritium breeding blanket (BB). Particularly in DEMO, high tritium extraction efficiency will be required in order to keep low the triti
Autor:
Tamas Ilkei, Andrea Ciampichetti, Fabio Cismondi, Bradut-Eugen Ghidersa, J.-F. Salavy, L. Kosek, A. Aiello
Publikováno v:
Fusion Engineering and Design. 86:602-606
The design of the auxiliary systems for the two European Test Blanket Modules is an important engineering task that will allow the successful integration of the two DEMO Blanket mock-ups into the ITER machine, and, through these experiments, demonstr