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R.M.Lambrecht*; Sekine, Toshiaki; H.Vera-Ruiz*
IAEA-TECDOC-1065, p.75 - 85, 1999/02
no abstracts in English
R.M.Lambrecht*; Sekine, Toshiaki; H.V.Ruiz*
Applied Radiation and Isotopes, 51(2), p.177 - 182, 1999/00
Times Cited Count:4 Percentile:34.39(Chemistry, Inorganic & Nuclear)no abstracts in English
T.V.Hung*
JAERI-Research 98-037, 14 Pages, 1998/07
no abstracts in English
Tanase, Masakazu; ;
Isotope News, 0(509), p.6 - 9, 1996/10
no abstracts in English
Isotope News, 0(508), p.12 - 15, 1996/09
no abstracts in English
; ; ; ; ; Tanase, Masakazu; Kurosawa, Kiyoyuki
Nihon Kagakkai-Shi, 0(10), p.888 - 894, 1996/00
no abstracts in English
Isotope News, 0(483), p.38 - 39, 1994/09
no abstracts in English
Ikeda, Yujiro; E.T.Cheng*; Konno, Chikara; Maekawa, Hiroshi
Nuclear Science and Engineering, 116, p.28 - 34, 1994/01
Times Cited Count:6 Percentile:51.78(Nuclear Science & Technology)no abstracts in English
Suematsu, Hisayuki*; Sato, Soma*; Nanko, Makoto*; Tsuchiya, Kunihiko; Nishikata, Kaori; Suzuki, Tsuneo*; Nakayama, Tadachika*; Niihara, Koichi*
no journal, ,
Spark plasma sintering of MoO was carried out for production of
Tc from
Mo by the (n,
) method in a nuclear reactor. Powder of MoO
with an average grain size of 0.8
m and a purity of 99.99% was pressed in a graphite die with a diameter of 20 mm. Then, the green compact was heated in a spark plasma sintering apparatus with heating rates of 100
200
C/min to 500
600
C in vacuum. After holding the temperature for 5 min, the sample was quenched. The sintered samples were characterized by powder X-ray diffraction for phase identifications, electron energy loss spectroscopy for compositional analyses and scanning electron microscopy for grain size measurements. After sintering at 550
C, a sintered bulk of MoO
with a relative density of 98% was obtained. These properties are good enough for separation of
Tc and recycle of Mo.
Tsuchiya, Kunihiko; Sozawa, Shizuo; Takeuchi, Nobuhiro*; Suzuki, Yasuaki*; Hasegawa, Yoshio*; Kakei, Sadanori*; Araki, Masanori
no journal, ,
Technetium-99m (Tc) is one of commonly used radioisotopes in the field of nuclear medicine. JAEA has a plan to produce
Mo by (n,
) method, a parent nuclide of
Tc in the Japan Material Testing Reactor (JMTR). In case of Japan, all of
Mo are imported from foreign countries, therefore JAEA has been performed the R&D on production of
Mo/
Tc in JMTR with Japanese industrial users under the cooperation programs. The R&D on
Mo/
Tc production was adopted as new project in Tsukuba International Strategic Zone, last year. In this project, various devices for production of
Tc solution will be equipped the hot cell in the JMTR Hot laboratory and the following R&D items will be carried out for the production improvement. (1) Fabrication of irradiation target such as the sintered MoO
pellets, (2) Separation and concentration of
Tc by the solvent extraction from Mo solution, (3) Examination of
Tc solution for a medicine, and (4) Mo recycling from Mo generator and solution. In this symposium, the status of the R&D and construction of the PIE devices under this project will be introduced for the production of
Mo/
Tc production improvement.
Tsuchiya, Kunihiko; Nishikata, Kaori; Kimura, Akihiro; Ishida, Takuya; Takeuchi, Nobuhiro*; Kobayashi, Masaaki*; Kawamura, Hiroshi
no journal, ,
no abstracts in English
Kawabata, Masako*; Hashimoto, Kazuyuki; Motoishi, Shoji*; Saeki, Hideya*; Shiina, Takayuki*; Ota, Akio*; Takeuchi, Nobuhiro*; Nagai, Yasuki
no journal, ,
no abstracts in English
Fujita, Yoshitaka; Seki, Misaki; Fujihara, Yasuyuki*; Suzuki, Tatsuya*; Yoshinaga, Hisao*; Takeuchi, Tomoaki; Nakano, Hiroko; Hori, Junichi*; Suematsu, Hisayuki*; Ide, Hiroshi
no journal, ,
no abstracts in English