Published May 1995 | Version v1
Report Open

TSTA/FCU-JFCU tritium experiment on breeding blanket interface under the collaboration of JAERI-US/DOE (extended Annex IV). March 1993

  • 1. Japan Atomic Energy Research Inst., Naka, Ibaraki (Japan). Naka Fusion Research Establishment

Description

In the extended Annex IV (1992-1994), it was aimed to perform realistic non-steady condition experiments of the fuel loop and Breeding Blanket Interface (BBI) experiments. It was proposed to use the combination process of Cryo-Molecular Sieve Bed (CMSB) and Palladium Diffuser (PD) for the recovery and purification of tritium in the Breeding Blanket purge stream. The BBI campaign experiment by using the CMSB of TSTA-FCU and the PD of JFCU was performed for the recovery of tritium from the simulated Breeding Blanket purge stream in the flow rate of 12.61/min. It was demonstrated that the proposed combination process has the feasibility as the Blanket Tritium Recovery System in fusion plant. This report summarizes the experimental result and analysis of the simulated BBI experiment. (author)

Availability note (English)

MF available from INIS under the Report Number.

Files

26075320.pdf

Files (933.2 kB)

Name Size Download all
md5:d3f6b28f28b4866c0b97dcf34c3e7868
933.2 kB Preview Download

Additional details

Publishing Information

Imprint Pagination
34 p.
Report number
JAERI-Research--95-034