Analysis of curium isotopes in mixed oxide fuel irradiated in fast reactor

Journal of Nuclear Science and Technology

Volumn 38, Issue 10, 2001, Pages 912-914

  Osaka, Masahiko ^a   Koyama, Shin Ichi ^a   Morozumi, Katsufumi ^a   Namekawa, Takashi ^a   Mitsugashira, Toshiaki ^b  

^a JAPAN ATOMIC ENERGY AGENCY   (Japan)

^b TOHOKU UNIVERSITY   (Japan)

Author keywords

Chemical separation; Curium isotopes; Fast reactors; Ion exchange; Irradiation; Isotopic analysis; Minor actinide; Mixed oxide fuels

Indexed keywords

CHEMICAL REACTORS; CHROMATOGRAPHIC ANALYSIS; ION EXCHANGE RESINS; IRRADIATION; METHANOL; NITROGEN OXIDES; RADIOACTIVITY; RADIOISOTOPES; TOXICITY;

MINOR ACTINIDES; RADIOTOXICITY; TRANSMUTATION;

CURIUM;

EID: 0035484463     PISSN: 00223131     EISSN: None     Source Type: Journal    
DOI: 10.1080/18811248.2001.9715116     Document Type: Article

References (6)

1. S. Koyama, Y. Otsuka, M. Osaka, et al., “Analysis of minor actinide in mixed oxide fuel irradiated in fast reactor, (I) Determination of neptunium-237,” J. Nucl. Sci. Technol., 35[6], 406 (1998).
2. S. Usuda, Studies on Rapid Ion-exchange Separation of the Transplutonium Elements with Mineral Acid-Methanol Mixed Media, JAERI 1315, Japan Atomic Energy Research Institute, (1988).
3. 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, Japan, (1997).
4. S. Tabuchi, T. Aoyama, H. Nagasaki, et al., JOYO MK-II Core Characteristics Database, JNC TN9410 99-003, Japan Nuclear Cycle Development Institute, (1998), [in Japanese].
5. A. G. Croff, A User’s Manualfor the ORIGEN2 Computer Code, ORNL-TM-7175, Oak Ridge National Laboratory, (1980).
6. 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, (1999), [in Japanese].