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Journal of Nuclear Science and Technology Volume 36, 1999 - Issue 6
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SHORT NOTE

Measurements of Neutron-induced Fission Cross Section of Protactinium-231 from 0.1 eV to 10 keV with Lead Slowing-down Spectrometer and at 0.0253 eV with Thermal Neutron Facility

Katsuhei KOBAYASHI Research Reactor Institute, Kyoto University , Kumatori-cho, Sennan-gun, Osaka-fu, 590-0494
,
Tetsuya KAI Research Reactor Institute, Kyoto University , Kumatori-cho, Sennan-gun, Osaka-fu, 590-0494
,
Shuji YAMAMOTO Research Reactor Institute, Kyoto University , Kumatori-cho, Sennan-gun, Osaka-fu, 590-0494
,
Hyun-Je CHO Research Reactor Institute, Kyoto University , Kumatori-cho, Sennan-gun, Osaka-fu, 590-0494
,
Hajimu YAMANA Research Reactor Institute, Kyoto University , Kumatori-cho, Sennan-gun, Osaka-fu, 590-0494
,
Yoshiaki FUJITA Research Reactor Institute, Kyoto University , Kumatori-cho, Sennan-gun, Osaka-fu, 590-0494
,
Toshiaki MITSUGASHIRA The Oarai-branch, Institute for Material Research, Tohoku University , Oarai-machi, Higashiibaraki-gun, Ibaraki-ken, 311-1313
&
Itsuro KIMURA Department of Nuclear Engineering, Kyoto University , Yoshida-honmachi, Sakyo-ku, Kyoto, 606-8501
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Pages 549-551 | Received 12 Feb 1999, Published online: 15 Feb 2012

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Shoji Nakamura, Yuji Shibahara, Shunsuke Endo & Atsushi Kimura. (2021) Thermal-neutron capture cross-section measurement of Tantalum-181 using graphite thermal column at KUR. Journal of Nuclear Science and Technology 58:10, pages 1061-1070.
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Hironobu UNESAKI, Tomohiko IWASAKI, Takanori KITADA, Yoshitaka IKEUCHI & Seiji SHIROYA. (2001) Measurement and Analysis of241 Am Fission Rate Ratio Relative to235 U Fission Rate in Thermal Neutron Systems Using Kyoto University Critical Assembly. Journal of Nuclear Science and Technology 38:8, pages 600-606.
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Articles from other publishers (1)

Tetsuya Kai, Katsuhei Kobayashi, Shuji Yamamoto, Hyun-Je Cho, Yoshiaki Fujita, Itsuro Kimura, Yasushi Ohkawachi & Toshio Wakabayashi. (2001) Measurements of neutron induced fission cross-section for 242mAm from 0.003 eV to 10 keV using lead slowing-down spectrometer, thermal neutron facility and time-of-flight method. Annals of Nuclear Energy 28:8, pages 723-739.
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