Zobrazeno 1 - 8
of 8
pro vyhledávání: '"Hirofumi Tomikawa"'
Autor:
Mitsuhiro Terakawa, Shuichiro Hayashi, Fumiya Morosawa, Hirofumi Tomikawa, Yo Nagano, Manan Machida, Hiroaki Onoe, Alexander Heisterkamp
Publikováno v:
Laser-based Micro- and Nanoprocessing XVI.
Autor:
Takuya Matsuki, Megumi Sekine, Koichi Tsutagi, Satoshi Suzuki, Takeshi Yasuda, Hirofumi Tomikawa, Hironobu Nakamura
Publikováno v:
Radiation Measurements. 124:74-78
In a reprocessing facility, it is required to develop a detector which can monitor plutonium (Pu) amount in the Pu solution containing the Fission Product (FP) in order to strengthen the safeguards capability. In order to investigate gamma rays which
Autor:
Yasunobu Mukai, Fabiana Rossi, Douglas Chase Rodriguez, Michio Seya, Kazuaki Nishimura, J. Takamine, Megumi Sekine, Hirofumi Tomikawa, Tsutomu Kurita, Satoshi Suzuki, Mitsuo Koizumi, Masafumi Tanigawa, Hironobu Nakamura
Publikováno v:
Journal of Nuclear Science and Technology. 55:792-804
Nuclear material in reprocessing facilities is safeguarded by random sample verification with additional process monitoring applied to solution masses and volumes within the tanks to maintain conti...
Autor:
Hirofumi Tomikawa, Megumi Sekine
Publikováno v:
Energy Procedia. 131:274-278
At a PUREX reprocessing facility, HNO3 solution with dissolved spent fuel, such as fission products (FP) and nuclear materials, flows in pipes and stores in tanks. To detect and deter the theft of nuclear materials from the aqueous process, measuring
Autor:
Yasushi Nauchi, Masao Komeda, Cynthia Heinberg, Taketeru Nagatani, Tomooki Shiba, Keiichiro Hori, Makoto Maeda, Masatoshi Kureta, Yoshihiro Kosuge, Keisuke Okumura, Hiroshi Sagara, Hirofumi Tomikawa
Publikováno v:
Energy Procedia. 131:258-263
This paper provides an interim report for characterization study of four candidate technologies for nuclear material quantification in fuel debris at Fukushima Daiichi Nuclear Power Station (1F). The severe loss-of-coolant accidents of 1F produced fu
Publikováno v:
Energy Procedia. 131:250-257
A simple but sufficiently accurate method for constructing a gamma-ray source for photon-transportation calculations is developed for canisters containing fuel debris from the Fukushima Daiichi nuclear power plant. The new method couples a baseline s
Publikováno v:
Journal of the Atomic Energy Society of Japan. 58:536-541
Publikováno v:
J. NUCL. SCI. TECHNOL.. 51(No. 1):1-23
The technologies applied to the analysis of the Three Mile Island accident were examined in a feasibility study of gamma spectrometry of molten core material from the Fukushima Daiichi Nuclear Power Station unit 1, 2, and 3 cores for special nuclear