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JAEA Reports

Research of the tasks on risk communication enforcement in fiscal year 2015 (Contract research)

Tanaka, Masaru*; Aoyama, Isao*; Ishizaka, Kaoru*; Ohata, Yuki*; Fukuike, Iori*; Kawase, Keiichi; Watanabe, Masanori; Tokizawa, Takayuki; Miyagawa, Hiroshi*; Ishimori, Yuu

JAEA-Research 2017-003, 65 Pages, 2017/06

JAEA-Research-2017-003.pdf:2.92MB

JAEA Ningyo-toge Environmental Engineering Center and Fukushima Environmental Safety Center have same challenges in risk communication. As reference, similar domestic cases were investigated by our two Centers, and requirements for building long-term relationship were clarified. As follows; (1) Develop new relationship with various stakeholders in the region. (2) Make better use of existing resources (personnel, land and facilities, etc.). (3) Make a concerted effort to create new values with local stakeholders. (4) Make an opportunity which local stakeholders confirm safety and build confidence to the project. These efforts will enhance the opportunities for operators and residents to learn about environment management and environmental protection.

JAEA Reports

Research of the tasks on risk communication enforcement (Contract research)

Tanaka, Masaru*; Aoyama, Isao*; Ishizaka, Kaoru*; Ohata, Yuki*; Fukuike, Iori*; Miyagawa, Hiroshi*; Ishimori, Yuu

JAEA-Research 2016-017, 76 Pages, 2017/01

JAEA-Research-2016-017.pdf:10.57MB

From 1955 to 2001, Japan Atomic Energy Agency (JAEA) carried out research and development projects related to uranium exploration, mining refining, conversion and enrichment at/around Ningyo-toge in Japan. Subsequently, JAEA has been conducting projects related to decommissioning of nuclear fuel cycle facilities and remediation of closed mine sites. JAEA had opportunities of communication with local stakeholders through the projects. Consensus building with local stakeholders and maintain it for over decades are important challenges for JAEA Ningyo-toge Environmental Engineering Center. For this aim, similar domestic case were investigated and compared, and evaluated about required measures for long term relationship with local stakeholder.

Journal Articles

Measurement of reaction rates in Li/V-alloy assembly with 14 MeV neutron irradiation

Tanaka, Teruya*; Sato, Satoshi; Kondo, Keitaro; Ochiai, Kentaro; Murata, Isao*; Takakura, Kosuke; Sato, Fuminobu*; Kada, Wataru*; Iida, Toshiyuki*; Konno, Chikara; et al.

Fusion Science and Technology, 60(2), p.681 - 686, 2011/08

 Times Cited Count:1 Percentile:10.73(Nuclear Science & Technology)

Irradiation experiments of 14 MeV neutrons have been performed on a Li block assembly of 46 $$times$$ 51 $$times$$ 51 cm$$^3$$ with a 5 cm thick V-alloy layer inside to examine the accuracy of neutronics calculations for the Li/V-alloy blanket design. Foils of Nb, Ni, In and Au for reaction rate measurements of $$^{93}$$Nb(n,2n)$$^{rm 92m}$$Nb, $$^{58}$$Ni(n,p)$$^{58}$$Co, $$^{115}$$In(n,n')$$^{rm 115m}$$In, $$^{197}$$Au(n,$$gamma$$)$$^{198}$$Au reactions and $$^6$$Li enriched ($$^6$$Li: 95.5%) and $$^7$$Li enriched ($$^7$$Li: 99.9%) Li$$_2$$CO$$_3$$ pellets for tritium production rate measurements were installed in the assembly. Results of the measurements were compared with those of calculations with MCNP5, JENDL-3.3 and JENDL/D-99. The comparisons for the reaction rates in the Nb, Ni and In foils indicate that measurements and calculations of the fast neutron transport are consistent almost within 10%. In the comparison for the reaction rates in the Au foils, the underestimation of 15% was found at a surface of the V-alloy layer. There is a possibility that this is due to the elastic scattering cross section of V around 4 keV as previously reported. The comparisons for tritium production rates in the $$^6$$Li enriched and $$^7$$Li enriched Li$$_2$$CO$$_3$$ pellets indicate that calculated rates were larger than results of the measurements by 2-8% and 1-4%, respectively.

Journal Articles

Scattering of $$^{11}$$Be halo nucleus from $$^{209}$$Bi at coulomb barrier

Mazzocco, M.*; Signorini, C.*; Romoli, M.*; De Francesco, A.*; Di Pietro, M.*; Vardaci, E.*; Yoshida, Koichi*; Yoshida, Atsushi*; Bonetti, R.*; De Rosa, A.*; et al.

European Physical Journal A, 28(3), p.295 - 299, 2006/06

 Times Cited Count:46 Percentile:90.03(Physics, Nuclear)

The scattering of the radioactive, weakly bound, halo nucleus $$^{11}$$Be from $$^{209}$$Bi has been studied at 40 MeV. The measurement performed with a low-intensity and a large-emittance secondary beam could be made using an extremely compact, large solid angle ($$sim$$ 2$$pi$$ sr) detecting set-up, based on 8 highly segmented Si telescopes. The $$^{9,11}$$Be scattering angular distributions, as well as their relative reaction cross-sections, resulted to be rather similar. This may suggest that at Coulomb barrier energies the halo structure and the small weakly binding energy of the $$^{11}$$Be projectile have no big influence on the reaction dynamics.

Journal Articles

Present status of JAEA-Tokai tandem accelerator

Matsuda, Makoto; Takeuchi, Suehiro; Tsukihashi, Yoshihiro; Hanashima, Susumu; Abe, Shinichi; Osa, Akihiko; Ishizaki, Nobuhiro; Tayama, Hidekazu; Nakanoya, Takamitsu; Kabumoto, Hiroshi; et al.

Proceedings of 3rd Annual Meeting of Particle Accelerator Society of Japan and 31st Linear Accelerator Meeting in Japan, p.275 - 277, 2006/00

no abstracts in English

Journal Articles

Measurement of radiation skyshine with D-T neutron source

Yoshida, Shigeo*; Nishitani, Takeo; Ochiai, Kentaro; Kaneko, Junichi*; Hori, Junichi; Sato, Satoshi; Yamauchi, Michinori*; Tanaka, Ryohei*; Nakao, Makoto*; Wada, Masayuki*; et al.

Fusion Engineering and Design, 69(1-4), p.637 - 641, 2003/09

 Times Cited Count:9 Percentile:53.35(Nuclear Science & Technology)

no abstracts in English

JAEA Reports

Desgin study of pyrochemical process operation by using virtual engineering models

Kakehi, Isao; Tozawa, Katsuhiro; ; ; *

JNC TN9400 2000-053, 99 Pages, 2000/04

JNC-TN9400-2000-053.pdf:7.47MB

This report describes accomplishment of simulations of Pyrochemical Process Operation by using virtual engineering models. The pyrochemical process using molten salt electrorefining would introduce new technologies for new fuels of particle oxide, particle nitride and metallic fuels. This system is a batch treatment system of reprocessing and re-fabrication, which transports products of solid form from a process to next process. As a result, this system needs automated transport system for process operations by robotics. ln this study, a simulation code system has been prepared, which provides virtual engineering environment to evaluate the pyrochemical process operation of a batch treatment system using handling robots. And the simulation study has been conducted to evaluate the required system functions, which are the function of handling robots, the interactions between robot and process equipment, and the time schedule of process, in the automated transport system by robotics. As a result of simulation of the process operation, which we have designed, the automated transport system by robotics of the pyrochemical process is realistic. And the issues for the system development have been pointed out.

Journal Articles

Generation of polyphenylene radical cations and their cosensitization ability in the 9,10-dicyanoanthracene-sensitized photochemical chain reactions of 1,2-bis(4-methoxyphenyl) cyclopropane

*; Ichinose, Yuji; *; Sasuga, Tsuneo; *; *

J. Org. Chem., 63(10), p.3204 - 3212, 1998/00

 Times Cited Count:24 Percentile:63.1(Chemistry, Organic)

no abstracts in English

Journal Articles

Diffractometer for neutron crystallography in biology

Niimura, Nobuo*; *; Minezaki, Yoshiaki; *; *; *; *; Hidaka, M.*; Minakawa, Nobuaki; Morii, Yukio

Physica B; Condensed Matter, 213-214, p.786 - 789, 1995/00

 Times Cited Count:18 Percentile:70.91(Physics, Condensed Matter)

no abstracts in English

Journal Articles

Development of remote dismantling and removal of large components in Reprocessing Plant

Ishibashi, Yuzo; Kawata, Tomio; Tanaka, Yasumasa; ;

Proceedings of 3rd International Conference on Nuclear Engineering (ICONE-3), p.0 - 0, 1995/00

None

Journal Articles

The Deterioration and the residual life time of O-ring seal which was used in a nuclear reactor

Ito, Masayuki; ; ; ; ;

Materiaru Raifu, 4(1), p.37 - 43, 1992/01

no abstracts in English

Journal Articles

Irradiation experience of power ramping test facility in JMTR

; ; ;

UTNL-R-0274, p.2-1 - 2-6, 1992/00

no abstracts in English

Journal Articles

Research and development of HTTR coated particle fuel

Fukuda, Kosaku; Ogawa, Toru; Hayashi, Kimio; Shiozawa, Shusaku; Tsuruta, Harumichi; ; *; *; *

Journal of Nuclear Science and Technology, 28(6), p.570 - 581, 1991/06

no abstracts in English

JAEA Reports

In-pile test of the crud separator system in the HBWR; Development of the crud separator system, II

; Iimura, Katsumichi; Yokouchi, Iichiro; Nakagawa, Tetsuya;

JAERI-M 90-231, 17 Pages, 1991/01

JAERI-M-90-231.pdf:0.8MB

no abstracts in English

JAEA Reports

Out-of-pile test of the crud separator system; Development of the crud separator system, I

; Iimura, Katsumichi;

JAERI-M 90-230, 20 Pages, 1991/01

JAERI-M-90-230.pdf:0.53MB

no abstracts in English

Journal Articles

Programmed temperature control of capsule in irradiation test with personal computer at JMTR

; Uramoto, Toshimasa; Fukushima, Masao; ; ; ;

Proc. of the 3rd Asian Symp. on Research Reactor, p.285 - 292, 1991/00

no abstracts in English

JAEA Reports

Evaluation of radiation-induced degradation of silicon O ring

; Ito, Masayuki; ; ; ;

JAERI-M 90-216, 40 Pages, 1990/12

JAERI-M-90-216.pdf:1.36MB

no abstracts in English

JAEA Reports

In-pile loop OWL-2 and irradiation tests done with it

; ; ; Watanabe, Hiroyuki; ;

JAERI-M 90-196, 45 Pages, 1990/11

JAERI-M-90-196.pdf:1.67MB

no abstracts in English

Journal Articles

Improvement in the temperature control method for irradiation capsules in the JMTR

; Endo, Yasuichi; ;

UTNL-R-0247, 6 Pages, 1990/00

no abstracts in English

JAEA Reports

In-pile loop OWL-2 and irradiation tests done with it

; ; Watanabe, Hiroyuki; ; ;

JAERI-M 89-043, 35 Pages, 1989/03

JAERI-M-89-043.pdf:1.41MB

no abstracts in English

44 (Records 1-20 displayed on this page)