Electrolytic reduction of Tc(VII) in nitric acid solution using glassy carbon electrode

Hoshi, Harutaka*; Wei, Y.*; Kumagai, Mikio*; Asakura, Toshihide; Morita, Yasuji

Journal of Radioanalytical and Nuclear Chemistry, 262(3), p.601 - 605, 2005/01

https://doi.org/10.1007/s10967-005-0482-6

Electroreduction of Tc(VII) in nitric acid solution using grassy carbon electrode was studied. The electroreduction was conducted at a constant potential -300 mV (vs. Ag/AgCl) with a potentiostat. It was found that difference of the Tc concentration in the solutions before and after the electrolysis was negligibly small. This means that there were almost no TcO or Tc deposited on the carbon fiber electrode during the electroreduction. Absorption spectra and distribution coefficients obtained by ion-exchange analysis indicated that Tc(VII) was reduced to Tc(IV).

Structural integrity assessment of helium component during safety demonstration test using HTTR, 1 (Contract Research)

Sakaba, Nariaki; Nakagawa, Shigeaki; Furusawa, Takayuki; Tachibana, Yukio

JAERI-Tech 2004-045, 67 Pages, 2004/04

JAERI-Tech-2004-045.pdf:4.74MB

Safety demonstration tests using the HTTR are now underway in order to verify the inherent safety features and to improve the safety design and evaluation technologies for HTGRs, as well as to contribute to research and development for the VHTR, which is one of the Generation IV reactors. In the safety demonstration tests, the coolant flow reduction test by tripping one or two out of three gas circulators is being performed between FY2002 and FY 2005 and by tripping all the three gas circulators will be conducted after FY2006. This paper describes the structural integrity assessment of the primary pressurised water cooler after one and two gas circulators run down. Also, the possibility of natural convection in the primary coolant after all the three gas circulator stopped was evaluated by the operation data of the reactor-scram test performed during the rise-to-power tests.

Safety demonstration tests using High Temperature Engineering Test Reactor (HTTR)

Tachibana, Yukio; Nakagawa, Shigeaki; Iyoku, Tatsuo

Proceedings of International Conference on Global Environment and Advanced Nuclear Power Plants (GENES4/ANP 2003) (CD-ROM), 8 Pages, 2003/09

no abstracts in English

Feasibility study of BWR-type reduced-moderation water reactor core design in thermal-hydraulic view point

Araya, Fumimasa; Kureta, Masatoshi; Akimoto, Hajime

Proceedings of 2nd Japan-Korea Symposium on Nuclear Thermal Hydraulics and Safety (NTHAS-2), p.309 - 314, 2000/00

no abstracts in English

An evaluation of the inlet flow reduction for a cable-in-conduit conductor in pulsed operation

Sugimoto, Makoto; Isono, Takaaki; Tsuji, Hiroshi; Yoshida, Kiyoshi; *; Hamajima, Takataro*; Sato, Takashi*; Shinoda, K.*

Cryogenics, 38(10), p.989 - 994, 1998/00

https://doi.org/10.1016/S0011-2275(98)00086-1

no abstracts in English

Transient burnout under rapid flow reduction condition

Journal of Nuclear Science and Technology, 24(10), p.811 - 820, 1987/10

https://doi.org/10.3327/jnst.24.811

no abstracts in English

Reduction of gas flow into a hollow cathode ion source for neutral beam injector

; ; *; ; *

Review of Scientific Instruments, 53(7), p.1038 - 1048, 1982/00

https://doi.org/10.1063/1.1137105

no abstracts in English

Burnout Tests During Flow Reduction Transients, Transient Flow Boiling Experiments at an Atmospheric Pressure,IV

;

JAERI-M 7489, 84 Pages, 1978/01

JAERI-M-7489.pdf:3.17MB

no abstracts in English