http://www.cnr.it/ontology/cnr/individuo/prodotto/ID25975
Design of a cooling system for the ITER Ion Source and Neutral Beam test facilities (Articolo in rivista)
- Type
- Label
- Design of a cooling system for the ITER Ion Source and Neutral Beam test facilities (Articolo in rivista) (literal)
- Anno
- 2009-01-01T00:00:00+01:00 (literal)
- Http://www.cnr.it/ontology/cnr/pubblicazioni.owl#doi
- 10.1016/j.fusengdes.2009.01.029 (literal)
- Alternative label
- Http://www.cnr.it/ontology/cnr/pubblicazioni.owl#autori
- M. Dalla Palma; S. Dal Bello; F. Fellin; P. Zaccaria (literal)
- Pagina inizio
- Pagina fine
- Http://www.cnr.it/ontology/cnr/pubblicazioni.owl#url
- http://www.sciencedirect.com/science/article/pii/S0920379609000647 (literal)
- Http://www.cnr.it/ontology/cnr/pubblicazioni.owl#numeroVolume
- Rivista
- Http://www.cnr.it/ontology/cnr/pubblicazioni.owl#note
- Http://www.cnr.it/ontology/cnr/pubblicazioni.owl#pagineTotali
- Note
- ISI Web of Science (WOS) (literal)
- Scopu (literal)
- Http://www.cnr.it/ontology/cnr/pubblicazioni.owl#affiliazioni
- Consorzio RFX, Associazione EURATOM-ENEA sulla Fusione, Corso Stati Uniti 4, I-35127 Padova, Italy (literal)
- Titolo
- Design of a cooling system for the ITER Ion Source and Neutral Beam test facilities (literal)
- Abstract
- This paper deals with the requirements, operational modes and design of the cooling system for the ITER
Neutral Beam test experiments. Different operating conditions of the experiments have been considered
in order to identify the maximum heat loads that constitute, with the inlet temperature and pressure at
each component, the design requirements for the cooling system.
The test facility components will be actively cooled by ultrapure water realizing a closed cooling loop
for each group of components. Electrochemical corrosion issues have been taken into account for the
design of the primary cooling loops and of the chemical and volume control system that will produce
water with controlled resistivity and pH. Draining and drying systems have been designed to evacuate
water from the components and primary loops in case of leakage, and to carry out leak detection.
Tritium concentration, water resistivity and pH will be measured and monitored at each primary loop
for safety reasons and high voltage holding reliability. The measured water flow rates and temperatures
will be used to calculate the exchanged heat fluxes and powers. Flow regulating valves and speed of
variable driven pumps will be adjusted to control the component temperatures in order to fulfil the
functional and thermohydraulic requirements. (literal)
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