Analysis of curium in mixed oxide fuel irradiated in the experimental fast reactor joyo for the evaluation of its transmutation behavior

Journal of Nuclear Science and Technology

Volumn 41, Issue 9, 2004, Pages 907-914

  Osaka, Masahiko ^a   Koyama, Shin Ichi ^a   Mitsugashira, Toshiaki ^b  

^a JAPAN ATOMIC ENERGY AGENCY   (Japan)

^b TOHOKU UNIVERSITY   (Japan)

Author keywords

Anion exchange; Chemical analysis; Curium; Fast reactor; Irradiated fuel; Methanol system; MOX fuel; Transmutation behavior

Indexed keywords

ANION-EXCHANGE; IRRADIATED FUELS; METHANOL SYSTEMS; MOX FUELS; TRANSMUTATIONS;

CHEMICAL ANALYSIS; FAST REACTORS; IONIZATION; IRRADIATION; MASS SPECTROMETRY; NUCLEAR FUELS; RADIOACTIVITY; THERMOANALYSIS;

CURIUM;

EID: 9144238963     PISSN: 00223131     EISSN: None     Source Type: Journal    
DOI: 10.1080/18811248.2004.9715563     Document Type: Article

References (16)

1. K. Aizawa, “R&D for fast reactor fuel cycle technologies in JNC,” Proc. Int. Conf. On Back-End of the Fuel Cycle, Paris, France, Sept. 9-13, 2001, p. 50 (2001).
2. K. Tanaka, S. Kono, K. Ono, “Conceptual design study of advanced fuel fabrication systems,” Proc. Int. Conf. On Back-End of the Fuel Cycle, Paris, France, Sept. 9-13, 2001, p. 58 (2001).
3. T. Iwasaki, N. Hirakawa, “Transmutation of minor actinide in well thermalized neutron field and application of advanced neutron source (ANS),” J. Nucl. Sci. Technol., 32[1], 8 (1995).
4. M. Wantschik, Bestimmung der Curiumbildung in Leichtwas-serreaktoren und Vergleich mit Berechnungen, KfK 3316, KfK, (1982), [in German].
5. L. Koch, R. Wellum, “Actinide evolution in LWR and FR,” Proc. 2nd Technical Meeting Nuclear Tranmutation Actinides, p. 153 (1980).
6. R. J. Guenther, D. E. Blahnik, T. K. Campbell, et al., Characterization of Spent Fuel Approved Testing Material-ATM-103, PNL-5109-103, PNL, (1988).
7. Dissolution Study Group in the Department of Chemistry, Dissolution Studies of Spent Nuclear Fuels, JAERI-M 91010, Japan Atomic Energy Research Institute (JAERI), (1991), [in Japanese].
8. V. I. Borisenkov, A. M. Mitin, A. P. Chetverikov, et al., “Accumulation of Am and Cm in fast reactor oxide fuel,” Radiokhimiya, 32[4], 8 (1991).
9. M. Osaka, S. Koyama, K. Morozumi, et al., “Analysis of curium isotopes in mixed oxide fuel irradiated in fast reactor,” J. Nucl. Sci Technol., 38[10], 912 (2001).
10. S. Koyama, M. Osaka, T. Sekine, et al., “Measurement of burn-up in FBR MOX fuel irradiated to high burn-up,” J. Nucl. Sci. Technol., 40[12], 998 (2003).
11. S. Koyama, Y. Otsuka, M. Osaka, et al., “Analysis of americium in irradiated MOX fuel by applying a new isolation technique based on americium oxidation,” Proc. Int. Conf. On Future Nuclear Systems, Yokohama, Japan, 1997, p. 1512 (1997).
12. Y. Ando, H. Takano, Estimation of LWR Spent Fuel Composition, JAERI-Research 99-004, Japan Atomic Energy Research Institute (JAERI), (1999), [in Japanese].
13. S. Tabuchi, T. Aoyama, H. Nagasaki, et al., JOYO Mk-II Core Characteristics Database, JNC TN9410 99-003, Japan Nuclear Cycle Development Institute (JNC), (1998), [in Japanese].
14. A. G. Croff, A User’s Manual for the ORIGEN2 Computer Code, ORNL-TM-7175, Oak Ridge National Laboratory (ORNL), (1980).
15. K. Suyama, J. Katakura, Y. Ohkawachi, et al., Libraries Based on JENDL-3.2 for ORIGEN2 Code ORLIBJ32, JAERI-Data/ Code 99-003, Japan Atomic Energy Research Institute (JAERI), (1999), [in Japanese].
16. W. S. Chalton, W. D. Stanbro, R. T. Perry, et al., “Comparisons of calculated and measured 237Np, 241 Am and 243 Am concentrations as a function of the 240Pu/239Pu isotopic ratio in spent fuel,” Nucl. Technol., 128, 285 (1999).