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Journal Articles

Characterization of hydrogen embrittlement of Ti and Ti-5Ta alloys using constant load test

Yokoyama, Kenichi*; Murata, Yusuke*; Shiimori, Fusae*; Sakai, Junichi*; Yamamoto, Masahiro; Uchiyama, Gunzo; Nojima, Yasuo*; Fujine, Sachio*

Fushoku Boshoku Kyokai Dai-58-Kai Zairyo To Kankyo Toronkai Koenshu, p.11 - 12, 2011/09

Characteristics of hydrogen embrittlement of pure Ti and Ti-5Ta alloys were evaluated by stress loading and constant load tests. Mechanical properties of these materials were affected by hydride formation of surface layers. Although elongation was reduced by hydrogen absorption, embrittlement was observed only in the surface hydride area. It is also suggested that Ti-5Ta alloy was better susceptibility of hydrogen embrittlement than pure Ti.

Journal Articles

Identified charged hadron production in $$p + p$$ collisions at $$sqrt{s}$$ = 200 and 62.4 GeV

Adare, A.*; Afanasiev, S.*; Aidala, C.*; Ajitanand, N. N.*; Akiba, Yasuyuki*; Al-Bataineh, H.*; Alexander, J.*; Aoki, Kazuya*; Aphecetche, L.*; Armendariz, R.*; et al.

Physical Review C, 83(6), p.064903_1 - 064903_29, 2011/06

 Times Cited Count:146 Percentile:99.38(Physics, Nuclear)

Transverse momentum distributions and yields for $$pi^{pm}, K^{pm}, p$$, and $$bar{p}$$ in $$p + p$$ collisions at $$sqrt{s}$$ = 200 and 62.4 GeV at midrapidity are measured by the PHENIX experiment at the RHIC. We present the inverse slope parameter, mean transverse momentum, and yield per unit rapidity at each energy, and compare them to other measurements at different $$sqrt{s}$$ collisions. We also present the scaling properties such as $$m_T$$ and $$x_T$$ scaling and discuss the mechanism of the particle production in $$p + p$$ collisions. The measured spectra are compared to next-to-leading order perturbative QCD calculations.

Journal Articles

Azimuthal correlations of electrons from heavy-flavor decay with hadrons in $$p+p$$ and Au+Au collisions at $$sqrt{s_{NN}}$$ = 200 GeV

Adare, A.*; Afanasiev, S.*; Aidala, C.*; Ajitanand, N. N.*; Akiba, Yasuyuki*; Al-Bataineh, H.*; Alexander, J.*; Aoki, Kazuya*; Aphecetche, L.*; Aramaki, Y.*; et al.

Physical Review C, 83(4), p.044912_1 - 044912_16, 2011/04

 Times Cited Count:8 Percentile:53.4(Physics, Nuclear)

Measurements of electrons from the decay of open-heavy-flavor mesons have shown that the yields are suppressed in Au+Au collisions compared to expectations from binary-scaled $$p+p$$ collisions. Here we extend these studies to two particle correlations where one particle is an electron from the decay of a heavy flavor meson and the other is a charged hadron from either the decay of the heavy meson or from jet fragmentation. These measurements provide more detailed information about the interaction between heavy quarks and the quark-gluon matter. We find the away-side-jet shape and yield to be modified in Au+Au collisions compared to $$p+p$$ collisions.

Journal Articles

Study of an aqueous process using hydrochloric acid for radioactive waste containing uranium

Ohashi, Yusuke; Tsunashima, Yasumichi; Murata, Masato

Proceedings of 2nd International Conference on Sustainable Development through Nuclear Research and Education (Nuclear 2009) (CD-ROM), p.161 - 168, 2009/05

Solid and liquid radioactive waste derived from various research such as technology development for uranium refining and conversion stored currently totals 1500tons. NaF waste, used as an absorbent of UF$$_{6}$$ contains about 20-30wt% uranium. CaF$$_{2}$$ waste, which is generated from the disposal of waste water including fluoride, contains up to 20wt% uranium. Most of these are classified as intermediate disposal waste. Hence it is necessary to recover uranium to dispose waste as a shallow ground disposal waste. Dissolution experiments were carried out by charging CaF$$_{2}$$ waste and NaF waste into 1N HCl. The dissolution rates of CaF$$_{2}$$ waste and NaF waste were 99.8% and 100% respectively. The recovery rates of uranium from CaF$$_{2}$$ solution and NaF solution were 98.2% and 99.7% respectively. It was confirmed that we could dispose these waste reasonably.

Journal Articles

Tritium behavior on a cultivated plot in the 1994 chronic HT release experiment at Chalk River

Noguchi, Hiroshi; Yokoyama, Sumi; Kinouchi, Nobuyuki; Murata, Mikio; Amano, Hikaru; Atarashi, Mariko; Ichimasa, Yusuke*; Ichimasa, Michiko*

Fusion Technology, 28, p.924 - 929, 1995/10

no abstracts in English

Oral presentation

Development of technology for treating and disposing of sludge contaminated with uranium, 2; Examination for recovering uranium from sludge contaminated with uranium by wet process

Ohashi, Yusuke; Nakatsuka, Yoshiaki; Kawatsuma, Shinji; Hata, Haruhi; Tsunashima, Yasumichi; Murata, Masato; Tokizawa, Takayuki; Sugitsue, Noritake

no journal, , 

Sludge waste derived from research and discussion for uranium refining and conversion exclude much uranium. We must recover uranium from them from the point of view of use of resource and we dispose of residue generated by the process. We recovered uranium from real waste by water or hydrochloric acid. The dissolution rates of uranium from sludge from neutralization and NaF, filter medium, alumina, MgF$$_{2}$$ wastes were more than 99% by 2 hour 1N HCl treatment. The dissolution rate of uranium from bed material waste was more than 99% by 24h 1N HCl treatment and addition of hydrogen peroxide. The dissolution rates of NaF, filter medium waste by water treatment were 99% and 88%. From the results, we confirmed dissolution characteristics of real waste as basic data to study recovery process of uranium.

Oral presentation

Development of technology for treating and disposing of sludge contaminated with uranium, 3; Confirmation examination for cement solidifications of sludge

Tsunashima, Yasumichi; Nakatsuka, Yoshiaki; Kawatsuma, Shinji; Ohashi, Yusuke; Murata, Masato; Tokizawa, Takayuki; Sugitsue, Noritake; Hata, Haruhi

no journal, , 

The operation waste generated from the uranium handling facilities of the uranium conversion and uranium enrichment, etc. is called a sludge. They are assumed to be execution of the uranium collection if necessary, cement solidification, and disposal. Therefore, the examination that confirmed the range where cement solidifies was executed. The cement kind, the water cement ratio, and the sludge mixture rate were assumed to be a parameter and the solidification test was executed. The range of solidification was confirmed by the bleeding water after 24 hours had passed. The uniaxial compression was measured with cement in the solidification condition. A possibility miscible from 40wt% to about 60wt% was able to be confirmed from these examination results in the absorbent (NaF pellet and active alumina), the bed materials (no active alumina), Neutralizing precipitation.

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