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Journal Articles

Measurements of neutronic characteristics of rectangular and cylindrical coupled hydrogen moderators

Kai, Tetsuya; Kamiyama, Takashi*; Hiraga, Fujio*; Oi, Motoki; Hirota, Katsuya*; Kiyanagi, Yoshiaki*

Journal of Nuclear Science and Technology, 55(3), p.283 - 289, 2018/03

 Times Cited Count:0 Percentile:0.01(Nuclear Science & Technology)

Journal Articles

Neutronic study on coupled hydrogen moderator for J-PARC spallation neutron source

Kai, Tetsuya; Harada, Masahide; Teshigawara, Makoto; Watanabe, Noboru; Ikeda, Yujiro

Proceedings of ICANS-XVI, Volume 3, p.657 - 666, 2003/07

Neutronic design studies were carried out on the J-PARC coupled H$$_{2}$$ moderator. The highest time- and energy- integrated intensity below 15 meV, pulse peak intensity at 2 meV and 10 meV, were given by 100% para-H$$_{2}$$ moderators, but the optimal moderator thickness was different for each: more than 220 mm, about 120 mm and 80 mm, respectively. Finally, we concluded 140 mm was the optimal thickness for the 100% para-H$$_{2}$$ coupled moderator. Cold neutron distributions on the moderator viewed surface were found to exhibit an intensity-enhanced region at a picture frame part near premoderator. This rather peculiar distribution suggested that the moderator and the viewed surface must be designed so as to take the brighter region near premoderator in use. The intensity decreases along with beam-extraction angle to the normal direction down to about 70% at 25.4$$^{rm o}$$. Then, we propose a cylindrical shape coupled moderator which brings about a slight intensity decrease for 0$$^{rm o}$$ but a increase in the averaged intensity over the angles of interest.

Journal Articles

Journal Articles

Some consideration of dose buildup factor for $$^{6}$$$$^{0}$$Co cylindrical source with shell-shaped shield

; *

Nuclear Science and Engineering, 33, p.340 - 341, 1968/00

 Times Cited Count:1

no abstracts in English

Oral presentation

Buckling evaluation method of Mod. 9Cr-1Mo steel cylinder under horizontal and vertical loads, 1; Effects of material properties and initial imperfection

Miura, Kazuhiro*; Okafuji, Takashi*; Sago, Hiromi*; Shimomura, Kenta; Okajima, Satoshi; Sato, Kenichiro*

no journal, , 

Buckling evaluation methods capable of evaluating elasto-plastic buckling under axial compression, bending, and shear loads are required for cylindrical vessels of fast reactors in order to cope with thinning due to the increase in diameter, adoption of new materials, and adoption of seismic isolation design due to the increase in the standard seismic ground motion. Buckling evaluation methods corresponding to the above are being considered in the fast reactor standards of the Japan Society of Mechanical Engineers. In this study, in order to examine the applicability of the proposed buckling evaluation equation, Monte Carlo simulation was carried out using material properties and initial imperfections, which are the fluctuation factors of buckling strength, as parameters, and the effect of the fluctuation of these factors on buckling load was evaluated. When the buckling load was normalized by the buckling critical value according to the proposed formula using the longitudinal elastic modulus and the design yield stress of JSME S NC2-2013, the 95% lower confidence limit exceeded the threshold of the proposed formula for both the vertical single load condition and the horizontal and vertical combined load condition. The results show that the buckling critical value calculated by using the design yield stress in the proposed equation is more conservative than the 95% lower confidence limit of the actual buckling load affected by the scatter of material properties and others.

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