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Journal Articles

Beam commissioning of the linac for iBNCT

Naito, Fujio*; Anami, Shozo*; Ikegami, Kiyoshi*; Uota, Masahiko*; Ouchi, Toshikatsu*; Onishi, Takahiro*; Oba, Toshiyuki*; Obina, Takashi*; Kawamura, Masato*; Kumada, Hiroaki*; et al.

Proceedings of 13th Annual Meeting of Particle Accelerator Society of Japan (Internet), p.1244 - 1246, 2016/11

The proton linac installed in the Ibaraki Neutron Medical Research Center is used for production of the intense neutron flux for the Boron Neutron Capture Therapy (BNCT). The linac consists of the 3-MeV RFQ and the 8-MeV DTL. Design average beam current is 10mA. Target is made of Beryllium. First neutron production from the Beryllium target was observed at the end of 2015 with the low intensity beam as a demonstration. After the observation of neutron production, a lot of improvement s was carried out in order to increase the proton beam intensity for the real beam commissioning. The beam commissioning has been started on May 2016. The status of the commissioning is summarized in this report.

Journal Articles

Fundamental study of the sulfide reprocessing process for oxide fuel, 1; Study on the Pu, MA and FP tracer-doped U$$_{3}$$O$$_{8}$$

Kirishima, Akira*; Mitsugashira, Toshiaki*; Onishi, Takashi; Sato, Nobuaki*

Journal of Nuclear Science and Technology, 48(6), p.958 - 966, 2011/06

 Times Cited Count:3 Percentile:26.02(Nuclear Science & Technology)

A novel reprocessing process based on the selective sulfurization of fission products (FP) has been proposed, where FP and minor actinides (MA) are first sulfurized by CS$$_{2}$$ gas, and then, dissolved by a dilute nitric acid solution. Consequently, the fuel elements are recovered as UO$$_{2}$$ and PuO$$_{2}$$. As a basic research of this new concept, the sulfurization and dissolution behaviors of U, Pu, Np, Am, Eu, Cs and Sr were investigated in this paper using $$^{236}$$Pu, $$^{237}$$Np, $$^{241}$$Am, $$^{152}$$Eu, $$^{137}$$Cs and $$^{85}$$Sr doped U$$_{3}$$O$$_{8}$$ sample by $$gamma$$ ray and $$alpha$$ spectrometries. The dependence of the dissolution ratio of each element on the sulfurization temperature was studied and reasonably explained by combining the information of the sulfide phase analysis and the chemical thermodynamics of the dissolution reaction. The sulfurization temperature ranging from 350 to 450 $$^{circ}$$C seems to be promising for the separation of FP and MA from U and Pu.

Journal Articles

Reliability evaluation of SPEEDI's prediction by comparison with calculated results based on meteorological observation data

Rintsu, Yuko*; Serizawa, Shigeru*; Yamazaki, Tetsuo*; Umeyama, Nobuaki*; Moriuchi, Shigeru*; Handa, Hiroyuki*; Onishi, Ryoichi*; Takemura, Morio*; Chino, Masamichi; Nagai, Haruyasu; et al.

Proceedings of 16th Pacific Basin Nuclear Conference (PBNC-16) (CD-ROM), 6 Pages, 2008/10

no abstracts in English

Journal Articles

Gamow-Teller decay of the $$T=1$$ nucleus $$^{46}$$Cr

Onishi, Takeo*; Gelberg, A.*; Sakurai, Hiroyoshi*; Yoneda, Kenichiro*; Aoi, Nori*; Imai, Nobuaki*; Baba, Hidetada*; Von Brentano, P.*; Fukuda, Naoki*; Ichikawa, Yuichi*; et al.

Physical Review C, 72(2), p.024308_1 - 024308_7, 2005/08

 Times Cited Count:21 Percentile:77.65(Physics, Nuclear)

no abstracts in English

Journal Articles

Status of research reactor decommissioning in Japan

Onishi, Nobuaki; Shirai, Eiji

Proc. of the 9th Pacific Basin Nuclear Conf., Vol. 2, p.1071 - 1076, 1994/00

no abstracts in English

Journal Articles

Neutron fluxes and spectra of the neutron guide tubes in the upgraded JRR-3

*; Suzuki, Masatoshi; Tsuruno, Akira; Onishi, Nobuaki

Physica B; Condensed Matter, 180-181, p.987 - 990, 1992/00

 Times Cited Count:7 Percentile:43.5(Physics, Condensed Matter)

no abstracts in English

Journal Articles

Construction of neutron guide tubes in upgraded JRR-3

; Suzuki, Masatoshi; Takahashi, Hidetake; Onishi, Nobuaki; *; *; *; *

Journal of Nuclear Science and Technology, 27(12), p.1138 - 1146, 1990/12

no abstracts in English

Journal Articles

Reconstruction and criticality experiment in new JRR-3

Onishi, Nobuaki; Takahashi, Hidetake; Takayanagi, Masaji; Ichikawa, Hiroki; Kawasaki, Minoru

Nihon Genshiryoku Gakkai-Shi, 32(10), p.962 - 969, 1990/10

 Times Cited Count:4 Percentile:47.14(Nuclear Science & Technology)

no abstracts in English

JAEA Reports

Design and construction of neutron guide tubes in JRR-3

Suzuki, Masatoshi; ; *; ; Onishi, Nobuaki; Takahashi, Hidetake; *; *; *; *; et al.

JAERI-M 90-079, 44 Pages, 1990/05

JAERI-M-90-079.pdf:1.99MB

no abstracts in English

Journal Articles

Transmission efficiency of the neutron guide tube with alignment errors

; Suzuki, Masatoshi; ; Harami, Taikan; Takahashi, Hidetake; Onishi, Nobuaki

Journal of Nuclear Science and Technology, 27(5), p.406 - 415, 1990/05

no abstracts in English

JAEA Reports

IDAS-RR, an Incident data base system for research reactors; Users manual

Matsumoto, Kiyoshi; Kosaka, Atsuo; Kaminaga, Masanori; Murayama, Yoji; Onishi, Nobuaki; *

JAERI-M 90-055, 232 Pages, 1990/03

JAERI-M-90-055.pdf:5.32MB

no abstracts in English

Journal Articles

Status and future of irradiation technique for fuel and structure component materials using research reactor

Enokido, Yuji*; *; *; Onishi, Nobuaki; ; Shiozawa, Shusaku

Nihon Genshiryoku Gakkai-Shi, 31(7), p.742 - 772, 1989/07

no abstracts in English

JAEA Reports

Energy deposition in NSRR silicide fuels

Soyama, Kazuhiko; Onishi, Nobuaki

JAERI-M 88-112, 33 Pages, 1988/06

JAERI-M-88-112.pdf:0.9MB

no abstracts in English

JAEA Reports

Accident analysis of flow blockage to coolant channels of upgraded JRR-3,using EUREKA-2 code,1

Kaminaga, Masanori; Murayama, Yoji; Onishi, Nobuaki

JAERI-M 88-001, 36 Pages, 1988/01

JAERI-M-88-001.pdf:0.95MB

no abstracts in English

Journal Articles

Reconstruction program for Japan Research Reactor-3

Onishi, Nobuaki; Isshiki, Masahiko; Takahashi, Hidetake;

Japan-China Symp. on Research and Test Reactors, 11 Pages, 1988/00

no abstracts in English

Journal Articles

One-piece removal of JRR-3 reaetor block

Onishi, Nobuaki

Nihon Genshiryoku Gakkai-Shi, 29(7), p.593 - 602, 1987/07

 Times Cited Count:0 Percentile:0.02(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Investigations related to a one-piece removal of the reactor block in the frame of the JRR-3 reconstruction program

Onishi, Nobuaki; ; ; Sakurai, Hiroshi

CONF-871018-Vol.2, p.6-95 - 6-105, 1987/00

no abstracts in English

Journal Articles

Evaluation of effective energy deposition in test fuel during power burst experiments in NSRR

Onishi, Nobuaki; Inabe, Teruo

Journal of Nuclear Science and Technology, 19(7), p.528 - 542, 1982/00

 Times Cited Count:10 Percentile:71.34(Nuclear Science & Technology)

no abstracts in English

Oral presentation

Fundamental research of nuclear fuel reprocessing by sulfurization reaction, 2; Process experiments using simulated spent nuclear fuel

Onishi, Takashi; Osaka, Masahiko; Miwa, Shuhei; Obayashi, Hiroshi; Sekino, Hirotaka*; Kirishima, Akira*; Sato, Nobuaki*

no journal, , 

As a demonstration of nuclear fuel reprocessing by sulfurization reaction, voloxidation, selective sulfurization and selective dissolution of simulated spent nuclear fuel pellet fabricated from U, Pu, Am and non-radioactive FP were conducted. As results, dissolution rate of each elements were obtained and behavior of MA and FP were investigated.

21 (Records 1-20 displayed on this page)