Development of a tritium fuel processing system using an electrolytic reactor for ITER

Autor:	T Yamanishi, Y Kawamura, Y Iwai, T Arita, T Maruyama, T Kakuta, S Konishi, M Enoeda, S Ohira, T Hayashi, H Nakamura, K Kobayashi, T Tadokoro, T Ito, M Yamada, T Suzuki, M Nishi, T Nagashima, M Ohta
Rok vydání:	2000
Předmět:	Nuclear and High Energy Physics Glow discharge Materials science Nuclear engineering chemistry.chemical_element Exhaust gas Cryogenics Electrolyte Condensed Matter Physics chemistry Physics::Plasma Physics Tritium Vacuum chamber Physics::Chemical Physics Diffuser (sewage) Helium
Zdroj:	Nuclear Fusion. 40:515-518
ISSN:	0029-5515
DOI:	10.1088/0029-5515/40/3y/311
Popis:	A system composed of a palladium diffuser and an electrolytic reactor has been proposed and then developed for the fuel cleanup system of ITER. The performance of the system has been studied in detail in a stand-alone test. A fuel simulation loop of ITER was constructed by connecting the fuel cleanup and hydrogen isotope separation systems developed; and the function of each system in the loop has been demonstrated. For tritium recovery from the exhaust gas during helium glow discharge cleaning of the vacuum chamber of ITER, a cryogenic molecular sieve bed system has been proposed and demonstrated.
Databáze:	OpenAIRE
Externí odkaz:	https://explore.openaire.eu/search/publication?articleId=doi_________::5e9743365d9d7ca79f3f9bc5a5f44470 https://doi.org/10.1088/0029-5515/40/3y/311 Zobrazit plný text záznamu