Disproportionation characteristics of a zirconium-cobalt hydride bed under iter operating conditions

Fusion Science and Technology

Volumn 53, Issue 3, 2008, Pages 830-840

  Shim, M ^a   Chung, H ^a   Cho, S ^a,b   Yoshid, H ^a,c  

^a Korea Atomic Energy Research Institute   (South Korea)

^b National Fusion Research Institute   (South Korea)

^c ITER Tritium Plant   (Japan)

Author keywords

Disproportionation; ITER SDS; ZrCo hydride bed

Indexed keywords

HYDROGEN; ISOTOPES; PLASMAS; PRESSURE EFFECTS; ZIRCONIUM;

DISPROPORTIONATION; HYDRIDE BED;

FUSION REACTIONS;

EID: 42349092016     PISSN: 15361055     EISSN: None     Source Type: Journal    
DOI: 10.13182/FST08-26     Document Type: Article

References (21)

1. H. YOSHIDA et al., "ITER R&D: Auxiliary Systems - Tritium Systems," Fusion Eng. Des., 55, 313 (2001).
2. ITER, EDA Document - Design Description Document 3.2: Tritium Plant" (2002).
3. M. DEVILLERS et al., "Hydrogen-Induced Disproportionation of the Intermetallic Compound ZrCo," Chem. Mater., 4, 631 (1992).
4. S. KONISHI et al., "Reversible Disproportionation of ZrCo under High Temperature and Hydrogen Pressure," J. Nucl. Mater., 223, 294 (1995).
5. U. A. BESSERER, "Tritiumspeicherung in ZrCo," Dissertation, Karlsruhe, Germany (2002).
6. M. HARA et al., "Kinetics and Mechanism of HydrogenInduced Disproportionation of ZrCo," Fusion Eng. Des., 49-50, 831 (2000).
7. K. WATANABE et al., "Stability of ZrCo and ZrNi to Heat Cycles in Hydrogen Atmosphere," Fusion Technol., 28, 1437 (1995).
8. ITER, EDA Final Design Documents - Design Requirements and Guidelines Level 1 (DRG 1) and Level 2 (DRG 2) (July 2001).
9. ITER, EDA Final Design Documents - Plant Description Document (PDD) (July 2001).
10. ITER, EDA Documentation Series No. 24, Chap. 3, IAEA, Vienna (2002).
11. M. H. SHIM et al., "Characteristics of ZrCo Alloy for the Storage of Hydrogen Isotopes," J. Korean Phys. Soc., 49, 369 (2006).
12. M. DEVILLERS et al., "Characterization of the ZrCo-Hydrogen System in View of Its Use for Tritium Storage," Chem. Mater., 2, 255 (1990).
13. T. HAYASHI et al., "Release Behavior of Decay Helium from Zirconium-Cobalt Tritide," Fusion Technol., 21, 845 (1992).
14. M. E. MALINOWSKI et al., "Helium Release from Uranium Tritide," Proc. Int. Conf. Radiation Effects and Tritium Technology for Fusion Reactors, Gatlinburg, Tennessee, October 1-3, 1975, Vol. IV, p. 53.
15. ITER Joint Central Team and Home Teams, EDA Document D-316 Final Report (1998).
16. S. O'HIRA et al., "Improvement of Tritium Accountancy Technology for the ITER Fuel Cycle Safety Enhancement," Nucl. Fusion, 40, 3Y, 519 (2000).
17. M. GLUGLA et al., "ITER Fuel Cycle R&D: Consequences for the Design," Fusion Eng. Des., 81, 733 (2006).
18. R. Lasser, Tritium and Helium-3 in Metals, Springer-Verlag, Berlin, Germany (1989).
19. T. HAYASHI et al., "Isotope Effect of Hydrogen Rapidly Supplied from the Metal Storage Bed," presented at 17th TOFE Meeting, Albuquerque, New Mexico, November 14, 2006.
20. N. BEKRIS et al., "On the Thermal Stability of the Zirconium/Cobalt-Hydrogen System," Fusion Eng. Des., 49-50, 781 (2000).
21. W. T. SHMAYDA et al., "Comparison of Uranium and Zirconium Cobalt for Tritium Storage," J. Less-Common Metals, 162, 117 (1990).