TSTA/FCU-JFCU tritium experiment on breeding blanket interface under the collaboration of JAERI-US/DOE (extended Annex IV). March 1993
Creators
- 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
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Additional details
Publishing Information
- Imprint Pagination
- 34 p.
- Report number
- JAERI-Research--95-034
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 26075320
- Subject category
- S70: PLASMA PHYSICS AND FUSION TECHNOLOGY;
- Descriptors DEI
- BREEDING BLANKETS; D-T REACTORS; THERMONUCLEAR REACTOR FUELING; TRITIUM; TRITIUM EXTRACTION PLANTS; TRITIUM RECOVERY; TRITIUM SYSTEMS TEST ASSEMBLY
- Descriptors DEC
- BETA DECAY RADIOISOTOPES; BETA-MINUS DECAY RADIOISOTOPES; HYDROGEN ISOTOPES; INDUSTRIAL PLANTS; ISOTOPE SEPARATION PLANTS; ISOTOPES; LIGHT NUCLEI; NUCLEAR FACILITIES; NUCLEI; ODD-EVEN NUCLEI; RADIOISOTOPES; TEST FACILITIES; THERMONUCLEAR REACTORS; YEARS LIVING RADIOISOTOPES