The neutral beam test facility cryopumping operation: preliminary analysis and design of the cryogenic system
The ITER neutral beam heating and current drive system is to be equipped with a cryosorption cryopump made up of 12 panels connected in parallel, refrigerated by 4.5 K 0.4 Mpa supercritical helium. The pump is submitted to a non homogeneous flux of H(2) or D(2) molecules, and the absorbed flux varies from 3 Pa.m[-3] to 35 Pa.m[-3] .s[-1]. In the frame of the "ITER first injectior and test facility CSU-EFDA task" (TW3-THHN-IITF1), th eITER reference cryosystem and cryoplant designs have been assessed and compared to optimized designs devoted to the Neutral Beam Test Facility (NBTF). The 4.5 K cryopanel, which has a mass of about 1000 kg, must be periodically regenerated up to 90 K and occasionally to 470 K. The cooldown time after regeneration depends strongly on the refrigeration capacity. Fast regeneration and cool-down of the cryopanels are not considered a priority for th etest facility operation, and an analysis of the consequences of a limited cold power refrigerator on the cooling down time has been carried out and will be discussed. This paper presents a preliminary evaluation of the NBTF cryoplant and the associated process flow diagram.
Bibliographic Reference: An oral paper given at: 20th International Cryogenic Engineering Conference Organised by: Center for International Scientific Exchanges, Beijing (CN) Held at: Beijing Friendship Hotel, Beijing (CN)
Availability: Available from Association EURATOM-CEA, Departement de Recherches sur la Fusion Controlee, CEA Cadarache, F-13108 St Paul-Lez-Durance, France Tel: (+33) 4 42 25 70 01; Fax: (+33) 4 42 25 64 21 E-mail: email@example.com
Record Number: 200417526 / Last updated on: 2004-06-11
Original language: en
Available languages: en