Safe handling experience of a tritium storage bed

Fusion Engineering and Design

Volumn 83, Issue 10-12, 2008, Pages 1429-1432

  Hayashi, T ^a   Suzuki, T ^a   Yamada, M ^a   Shu, W ^a   Yamanishi, T ^a  

^a Directorates of Fusion Energy Research   (Japan)

Author keywords

Disproportionation; ITER; Storage bed; TPL; Tritide; Tritium; ZrCo

Indexed keywords

ACTINIDES; COBALT; EXPERIMENTAL REACTORS; HELIUM; HYDROGEN; HYDROGEN STORAGE; METAL RECOVERY; SULFUR COMPOUNDS; TRANSITION METALS; TRANSURANIUM ELEMENTS; TRITIUM; URANIUM; ZIRCONIUM;

DISPROPORTIONATION; ITER; STORAGE BED; TPL; TRITIDE; ZRCO;

SAFE HANDLING;

EID: 56949107728     PISSN: 09203796     EISSN: None     Source Type: Journal    
DOI: 10.1016/j.fusengdes.2008.07.010     Document Type: Article

References (23)

1. ITER Technical Basis, ITER EDA Documentation Series 24, IAEA, Vienna, 2002.
2. Nishi M., Yamanishi T., Hayashi T., and DEMO Plant Design Team. Study on tritium accountancy in fusion DEMO plant at JAERI. Fusion Eng. Des. 81 (2006) 745-751
3. Tobita K., Nishio S., Sato M., Sakurai S., Hayashi T., Shibama Y.K., Isono T., Enoeda M., Nakamura H., Sato S., Ezato K., Hayashi T., Hirose T., Ide S., Inoue T., Kamada Y., Kawamura Y., Kawashima H., Koizumi N., Kurita G., Nakamura Y., Mouri K., Nishitani T., Ohmori J., Oyama N., Sakamoto K., Suzuki S., Suzuki T., Tanigawa H., Tsuchiya K., and Tsuru D. Slim CS-compact low aspect ratio DEMO reactor with reduced-size central solenoid. Nucl. Fusion 47 (2007) 892-899
4. Naruse Y., Matsuda Y., and Tanaka K. Tritium Process Laboratory at the JAERI. Fusion Eng. Des. 12 (1990) 293-317
5. Schira P., Hutter E., Jourdan G., and Penzhorn R.-D. The tritium laboratory Karlsruhe; laboratory design and equipment. Fusion Eng. Des. 18 (1991) 19-26
6. Final Safety Analysis Report on Tritium Systems Test Assembly at the Loa Alamos National Laboratory, TSTA-SAR, Los Alamos National Laboratory, U.S.A., 1996.
7. Lasser R., Bell A.C., Baibridge N., Brennan P.D., Grieveson B., Hemmerich J.L., Jones G., Kennedy D., Knipe S., Lupo J., Mart J., Perevezentsev A., Skinner N., Stagg R., Yorkshades J., Atkins G.V., Dorr J., Green N., Stead M., and Wilson K. Overview of the performance of the JET active gas handling system during and after DTE1. Fusion Eng. Des. 47 (1999) 173-203
8. Anderson J.L., Gentile C., Kalish M., Kamperschroer J., Kozub T., LaMarche P., Murray H., Nagy A., Raftopoulos S., Rossmassler R., Sissingh R., Swanson J., Tulipano F., Viola M., Voorheers D., and Walters R.T. Operation of the tokamak fusion test reactor tritium systems during initial tritium experiments. Fusion Eng. Des. 28 (1995) 209-214
9. Nagasaki T., Konishi S., Katsuta H., and Naruse Y. A zirconium-cobalt compound as the material for a reversible tritium getter. Fusion Technol. 9 (1985) 506-509
10. Konishi S., Nagasaki T., Yokokawa N., and Naruse Y. Development of ZrCo beds for recovery, storage and supply of tritium. Fusion Eng. Des. 10 (1989) 355-358
11. Hayashi T., Suzuki T., Yamada M., and Nishi M. Tritium accounting stability of ZrCo bed with "in-bed" gas flowing calorimetry. Fusion Sci. Technol. 48 (2005) 317-323
12. Ohira S., Hayashi T., Nakamura H., Kobayashi K., Tadokoro T., Nakamura H., Itoh T., Yamanishi T., Kawamura Y., Iwai Y., Arita T., Maruyama T., Kakuta T., Konishi S., Enoeda M., Yamada M., Suzuki T., Nishi M., Nagashima T., and Ohta M. Improvement of tritium accountancy technology for ITER fuel cycle safety enhancement. Nucl. Fusion 40 (2000) 519-525
13. Hayashi T., Suzuki T., Konishi S., Yamanishi T., Nishi M., and Kurita K. Development of ZrCo beds for ITER tritium storage and delivery. Fusion Sci. Technol. 41 (2002) 801-804
14. Konishi S., Nagasaki T., and Okuno K. Reversible disproportionation of ZrCo under high temperature and hydrogen pressure. J. Nucl. Mater. 223 (1995) 294-299
15. Penzhorn R.-D., Devillers M., and Sirch M. Evaluation of ZrCo and other getters for tritium handling and storage. J. Nucl. Mater. 170 (1990) 217-231
16. Bekris N., Besserer U., Sirch M., and Penzhorn R.-D. On the thermal stability of the zirconium/cobalt-hydrogen system. Fusion Eng. Des. 49-50 (2000) 781-789
17. Besserer U., Penzhorn R.-D., and Brandt R. The behavior of zirconium-cobalt as a material for tritium storage. Fusion Sci. Technol. 41 (2002) 793-796
18. Glugla M., Murdoch D.K., Antipenkov A., Beloglazov S., Cristescu I., Cristescu I.-R., Day C., Lasser R., and Mack A. ITER fuel cycle R&D: consequences for the design. Fusion Eng. Des. 81 (2006) 733-744
19. Hara M., Okabe T., Mori K., and Watanabe K. Kinetics and mechanism of hydrogen-induced disproportionation of ZrCo. Fusion Eng. Des. 49-50 (2000) 831-838
20. Lasser R., Dorr L., Glugla M., Penzhorn R.-D., Hayashi T., Murdoch D.K., and Yoshida H. The storage and delivery system of the ITER tritium fuel processing plant. Fusion Sci. Technol. 41 (2002) 854-858
21. 3He release behavior from ZrCo tritide. J. Nucl. Mater. 212-215 (1994) 1431-1435
22. M. Glugla, Head of ITER Tritium Plant Group, private communication, February 2008.
23. Lasser R. Tritium and helium-3 in metals. Springer Series in Materials Science vol. 9 (1989), Springer-Verlag, Berlin Heifelbergm