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Journal Articles

Poly(ether ether ketone) (PEEK)-based graft-type polymer electrolyte membranes having high crystallinity for high conducting and mechanical properties under various humidified conditions

Hamada, Takashi; Hasegawa, Shin; Fukasawa, Hideyuki*; Sawada, Shinichi; Koshikawa, Hiroshi; Miyashita, Atsumi; Maekawa, Yasunari

Journal of Materials Chemistry A, 3(42), p.20983 - 20991, 2015/11

 Times Cited Count:27 Percentile:70.78(Chemistry, Physical)

no abstracts in English

Journal Articles

Proton conduction properties of crosslinked PTFE electrolyte membranes with different graft-chain structures

Sawada, Shinichi; Yamaki, Tetsuya; Asano, Masaharu; Terai, Takayuki*; Yoshida, Masaru

Transactions of the Materials Research Society of Japan, 30(4), p.943 - 946, 2005/12

We synthesized crosslinked-polytetrafluoroethylene (PTFE) electrolyte membranes by a radiation grafting technique under different conditions, and then investigated their proton conduction properties at controlled temperatures and relative humidities (R.H.) by an AC impedance method. The density and length of graft chains were controlled by varying the pre-irradiation dose and grafting time, respectively. When the pre-irradiation dose was fixed at 15 kGy to make the graft chains an uniform density, the elongation of the graft chain increased the ion exchange capacity (IEC), there by enhancing their proton conductivity. The membrane with an IEC of 2.8 meq/g possessed the maximum conductivity reaching 0.20 S/cm at 80 $$^{circ}$$C and R.H. 95%. At almost the same IEC, membranes with more and shorter graft chains showed higher conductivity than those with less and longer chains. This result was probably related to the different structures of hydrophilic domains as proton-conducting pathways.

JAEA Reports

Report of Workshop on Energy; May 13, 2004, JAERI, Tokyo, Japan

Tsujimoto, Kazufumi; Nagai, Yasuki

JAERI-Review 2005-004, 208 Pages, 2005/03

JAERI-Review-2005-004.pdf:82.79MB

The Working Group on Energy (WG) was organized under International Union of Pure and Applied Physics (IUPAP). The WG has been considering problems on future energy supply and role of physics to solve the subjects. As one of activities of the WG, a Workshop on Energy was held on May 13, 2004 at Center for Promotion of Computational Science and Engineering, Japan Atomic Energy Research Institute (JAERI) in Tokyo hosted by IUPAP and co-hosted by JAERI and High Energy Accelerator Research Organization. The objectives of this workshop are to suggest active contributions of pure and applied physics field to the solution of the energy problem and to advance research and development (R&D) of future energy through the discussions about present status, problem and prospect of different energy development in the world and in Japan. This report records the summary of the Workshop and, abstracts and materials of 12 presentations. After the invited presentations about overview of energy problems in the world, in China and in Japan, R&D activities on the following four fields were presented; "Research and Development of New Energy", "Research and Development of Fusion Energy", "Prospect of Accelerator Driven System (ADS)", and "Hydrogen Production, Storage and Transportation".

JAEA Reports

Development of fission gas measurement technique in the irradiated fuel pellet

Hatakeyama, Yuichi; Sudo, Kenji; Kanazawa, Hiroyuki

JAERI-Tech 2004-033, 29 Pages, 2004/03

JAERI-Tech-2004-033.pdf:1.65MB

The amount of fission gas (Kr, Xe) in irradiated fuel pellet increases with extending the burn up and that exerts a serious influence upon thermal and mechanical properties of light water reactor fuel. Therefore, the accumulation of the data on the release behavior of fission gas is important in the investigation program of safety and reliability for extended burn up fuel. In the post irradiation examination at the Reactor Fuel Examination Facility in JAERI,the fission gas which released into the plenum region from UO$$_{2}$$ pellet during irradiation has been measured by puncturing test of irradiated fuel rod. The results of puncturing test show the most of fission gas remained in the pellet. It can be seen that the additional release of fission gas might occur under higher burn up and accident conditions. To know the fission gas release behavior from irradiated fuel, the Out Gas analyzer(OGA)which has the performance to heat up the UO$$_{2}$$ pellet stepwise up to 2300$$^{circ}$$C and to measure the released fission gas instantly from the pellet has been developed and installed at RFEF.

JAEA Reports

Study on the analyses of the reactor physics benchmark problem for the LWR next generation fuels

Research Committee on Reactor Physics

JAERI-Research 2004-004, 409 Pages, 2004/03

JAERI-Research-2004-004.pdf:28.53MB

This report summarizes the second phase (FY2001-2002) activity of "the Working Party (WP) on Reactor Physics for LWR Next Generation Fuels". The next generation fuels mean the ones aiming at further extended burn-up such as 70GWd/t over the current design. In the WP, the benchmark activity has been conducted to investigate and improve the calculation accuracy of the nuclear characteristics of the next generation fuels. In the second phase activity, all benchmark results were compiled and compared. Based on the comparison, the present status of calculation accuracy for the next generation fuels has been confirmed, and the factors causing the calculation differences were analyzed in detail. Moreover, analyses of the post irradiation and critical experiments with the codes used in the benchmark were reviewed, and future experiments and research subjects necessary to reduce the calculation differences were discussed and proposed.

Journal Articles

Update status of benchmark activity for reactor physics study of LWR next generation fuels

Unesaki, Hironobu*; Okumura, Keisuke; Kitada, Takanori*; Saji, Etsuro*

Transactions of the American Nuclear Society, 88, p.436 - 438, 2003/06

In order to investigate the calculation accuracy of the nuclear characteristics of LWR next generation fuels, the Research Committee on Reactor Physics organized by JAERI has proposed "Reactor Physics Benchmark for LWR Next Generation Fuels". The next generation fuels aim at very high burn-up of about 70GWd/t in PWR or BWR with UO$$_{2}$$ or MOX fuels whose fissile enrichments may exceed the Japanese regulatory limitations for the current LWR fuels such as 5wt.% U-235. Until now, twelve organizations have pariticipated in the benchmark activity. From the comparison with the cell burn-up calculation results using different codes and library data, status of the calculation accuracy and future subjects are clarified.

Journal Articles

Benchmark results of burn-up calculation for LWR next generation fuels

Okumura, Keisuke; Unesaki, Hironobu*; Kitada, Takanori*; Saji, Etsuro*

Proceedings of International Conference on the New Frontiers of Nuclear Technology; Reactor Physics, Safety and High-Performance Computing (PHYSOR 2002) (CD-ROM), 10 Pages, 2002/10

In order to investigate the calculation accuracy of the nuclear characteristics of LWR next generation fuels, the Research Committee on Reactor Physics organized by Japan Atomic Energy Research Institute has proposed "Reactor Physics Benchmark for LWR Next Generation Fuels". The next generation fuels aim at very high burn-up of about 70GWd/t in PWR or BWR with UO2 or MOX fuels whose fissile enrichments may exceed the Japanese regulatory limitations for the current LWR fuels such as 5wt.% U-235. Twelve organizations have carried out the analyses of the benchmark problems with different codes and data, and their submitted results have been compared. As a result, status of accuracy with the current data and method and some problems to be solved in the future were clarified.

JAEA Reports

Design of high temperature irradiation materials inspection cells (spent fuel inspection cells) in the High Temperature engineering Test Reactor

Ino, Hiroichi*; Ueta, Shohei; Suzuki, Hiroshi; Tobita, Tsutomu*; Sawa, Kazuhiro

JAERI-Tech 2001-083, 46 Pages, 2002/01

JAERI-Tech-2001-083.pdf:6.31MB

no abstracts in English

JAEA Reports

Proposal and analysis of the benchmark problem suite for reactor physics study of LWR next generation fuels

Research Committee on Reactor Physics

JAERI-Research 2001-046, 326 Pages, 2001/10

JAERI-Research-2001-046.pdf:14.45MB

The Working Party on Reactor Physics for LWR Next Generation Fuels in the Research Committee on Reactor Physics, which is organized by the Japan Atomic Energy Research Institute, has recently proposed a series of benchmark problems to investigate the calculation accuracy of the nuclear characteristics of LWR next generation fuels. The next generation fuels mean the ones aiming for further extended burnup such as 70GWd/t over the current design. The resultant specifications of the benchmark problem therefore neglect some of the current limitations such as 5wt%235U to achieve the above-mentioned target. The Working Party proposed six benchmark problems, which consist of pin-cell, PWR assembly and BWR assembly geometries loaded with uranium and MOX fuels, respectively. The present report describes the detailed specifications of the benchmark problems. The results of preliminary analyses performed by the eleven member organizations and their comparisons are also presented.

JAEA Reports

Present status of research on hydrogen energy and perspective of HTGR hydrogen production system

Miyamoto, Yoshiaki; Ogawa, Masuro; Akino, Norio; Shiina, Yasuaki; Inagaki, Yoshiyuki; Shimizu, Saburo; Onuki, Kaoru; Ishiyama, Shintaro; Katanishi, Shoji; Takeda, Tetsuaki; et al.

JAERI-Review 2001-006, 147 Pages, 2001/03

JAERI-Review-2001-006.pdf:9.2MB

no abstracts in English

JAEA Reports

SRAC95; General purpose neutronics code system

Okumura, Keisuke; *;

JAERI-Data/Code 96-015, 445 Pages, 1996/03

JAERI-Data-Code-96-015.pdf:12.94MB

no abstracts in English

Journal Articles

Effect of fuel grain size on reactivity

Okuno, Hiroshi; Naito, Yoshitaka; Sakurai, Y.*

Journal of Nuclear Science and Technology, 28(10), p.958 - 960, 1991/10

no abstracts in English

Journal Articles

Hexagonal lattice geometry for Monte Carlo calculations

Nakakawa, Masayuki; Mori, Takamasa; *

Annals of Nuclear Energy, 18(8), p.467 - 477, 1991/00

 Times Cited Count:1 Percentile:20.44(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Developments of tritium technology for next-step fusion devices under JAERI-DOE(LANL) collaboration

Naruse, Yuji; Okuno, Kenji; Yoshida, Hiroshi; Konishi, Satoshi; Anderson, J. L.*; Bartlit, J. R.*

Journal of Nuclear Science and Technology, 27(12), p.1081 - 1095, 1990/12

no abstracts in English

JAEA Reports

DELIGHT-7; One dimensional fuel cell burnup analysis code for High Temperature Gas-Cooled Reactors (HTGR)

Shindo, Ryuichi; Yamashita, Kiyonobu; Murata, Isao

JAERI-M 90-048, 225 Pages, 1990/03

JAERI-M-90-048.pdf:5.06MB

no abstracts in English

JAEA Reports

Journal Articles

Ethanol production and the effect of porous polymer carriers on immobilized growing yeast cells by radiation-induced polymerization

Fujimura, Takashi; Kaetsu, Isao

Int.J.Appl.Radiat.Isot., 34(6), p.929 - 931, 1983/00

 Times Cited Count:13 Percentile:91.64(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Decomposition of tritiated water with solid oxide electrolysis cell

Konishi, Satoshi; ; ; Naruse, Yuji

Nucl.Technol./Fusion, 3, p.195 - 198, 1983/00

no abstracts in English

Journal Articles

PIE of HTGR fuels and materials; Dimension measuring equipment of OGL-1 irradiated fuels

; ; ;

Proc.30th Conf.on Remote Systems Technology,Vol.2, p.33 - 36, 1982/00

no abstracts in English

23 (Records 1-20 displayed on this page)