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Journal Articles

Pyroelectric power generation from the waste heat of automotive exhaust gas

Kim, J.*; Yamanaka, Satoru*; Murayama, Ichiro*; Kato, Takanori*; Sakamoto, Tomokazu*; Kawasaki, Takuro; Fukuda, Tatsuo; Sekino, Toru*; Nakayama, Tadachika*; Takeda, Masatoshi*; et al.

Sustainable Energy & Fuels (Internet), 4(3), p.1143 - 1149, 2020/03

 Times Cited Count:2 Percentile:32.54(Chemistry, Physical)

Journal Articles

Electrical and crystallographic study of an electrothermodynamic cycle for a waste heat recovery

Kim, J.*; Yamanaka, Satoru*; Nakajima, Akira*; Kato, Takanori*; Kim, Y.*; Fukuda, Tatsuo; Yoshii, Kenji; Nishihata, Yasuo; Baba, Masaaki*; Takeda, Masatoshi*; et al.

Advanced Sustainable Systems (Internet), 2(11), p.1800067_1 - 1800067_8, 2018/11

 Times Cited Count:1 Percentile:82.92(Green & Sustainable Science & Technology)

Journal Articles

Temperature stability of PIN-PMN-PT ternary ceramics during pyroelectric power generation

Moro, Takuya*; Kim, J.*; Yamanaka, Satoru*; Murayama, Ichiro*; Kato, Takanori*; Nakayama, Tadachika*; Takeda, Masatoshi*; Yamada, Noboru*; Nishihata, Yasuo; Fukuda, Tatsuo; et al.

Journal of Alloys and Compounds, 768, p.22 - 27, 2018/11

 Times Cited Count:7 Percentile:35.32(Chemistry, Physical)

Journal Articles

Pyroelectric power generation with ferroelectrics (1-x)PMN-xPT

Kim, J.*; Yamanaka, Satoru*; Nakajima, Akira*; Kato, Takanori*; Kim, Y.*; Fukuda, Tatsuo; Yoshii, Kenji; Nishihata, Yasuo; Baba, Masaaki*; Takeda, Masatoshi*; et al.

Ferroelectrics, 512(1), p.92 - 99, 2017/08

 Times Cited Count:6 Percentile:50.14(Materials Science, Multidisciplinary)

Journal Articles

Relationship between the material properties and pyroelectric-generating performance of PZTs

Yamanaka, Satoru*; Kim, J.*; Nakajima, Akira*; Kato, Takanori*; Kim, Y.*; Fukuda, Tatsuo; Yoshii, Kenji; Nishihata, Yasuo; Baba, Masaaki*; Yamada, Noboru*; et al.

Advanced Sustainable Systems (Internet), 1(3-4), p.1600020_1 - 1600020_6, 2017/04

no abstracts in English

Journal Articles

Novel electrothermodynamic power generation

Kim, Y.*; Kim, J.*; Yamanaka, Satoru*; Nakajima, Akira*; Ogawa, Takashi*; Serizawa, Takeshi*; Tanaka, Hirohisa*; Baba, Masaaki*; Fukuda, Tatsuo; Yoshii, Kenji; et al.

Advanced Energy Materials, 5(13), p.1401942_1 - 1401942_6, 2015/07

An innovative electro-thermodynamic cycle based on temporal temperature variations using pyroelectric effect has been presented. Practical energy is successfully generated in both $textit{in-situ}$ synchrotron X-ray diffraction measurements under controlled conditions and $textit{Operando}$ real engine dynamometer experiments. The main generating origin is revealed as a combination of a crystal structure change and dipole change phenomenon corresponds to the temperature variation. In particular, the electric field induced 180$$^circ$$ domain switching extremely improves generating power, and the true energy breakeven with temperature variation is firstly achieved.

Journal Articles

Current status of a new polarized neutron reflectometer at the intense pulsed neutron source of the Materials and Life Science Experimental Facility (MLF) of J-PARC

Takeda, Masayasu; Yamazaki, Dai; Soyama, Kazuhiko; Maruyama, Ryuji; Hayashida, Hirotoshi; Asaoka, Hidehito; Yamazaki, Tatsuya; Kubota, Masato; Aizawa, Kazuya; Arai, Masatoshi; et al.

Chinese Journal of Physics, 50(2), p.161 - 170, 2012/04

Journal Articles

Applications of $$^{3}$$He neutron spin filters on the small-angle neutron scattering spectrometer SANS-J-II

Sakaguchi, Yoshifumi; Kira, Hiroshi; Oku, Takayuki; Shinohara, Takenao; Suzuki, Junichi; Sakai, Kenji; Nakamura, Mitsutaka; Aizawa, Kazuya; Arai, Masatoshi; Noda, Yohei; et al.

Journal of Physics; Conference Series, 294(1), p.012017_1 - 012017_7, 2011/06

 Times Cited Count:2 Percentile:29.95

Journal Articles

Structure of glasses for $$^{3}$$He neutron spin filter cells

Sakaguchi, Yoshifumi; Kira, Hiroshi; Oku, Takayuki; Shinohara, Takenao; Suzuki, Junichi; Sakai, Kenji; Nakamura, Mitsutaka; Suzuya, Kentaro; Aizawa, Kazuya; Arai, Masatoshi; et al.

Journal of Physics; Conference Series, 294(1), p.012004_1 - 012004_7, 2011/06

 Times Cited Count:1 Percentile:47.21

Journal Articles

Research on glass cells for $$^{3}$$He neutron spin filters

Sakaguchi, Yoshifumi; Kira, Hiroshi; Oku, Takayuki; Shinohara, Takenao; Suzuki, Junichi; Sakai, Kenji; Nakamura, Mitsutaka; Suzuya, Kentaro; Aizawa, Kazuya; Arai, Masatoshi; et al.

Physica B; Condensed Matter, 406(12), p.2443 - 2447, 2011/06

Journal Articles

Research on glass cells for $$^{3}$$He neutron spin filters

Sakaguchi, Yoshifumi; Kira, Hiroshi; Oku, Takayuki; Shinohara, Takenao; Suzuki, Junichi; Sakai, Kenji; Nakamura, Mitsutaka; Suzuya, Kentaro; Aizawa, Kazuya; Arai, Masatoshi; et al.

Physica B; Condensed Matter, 406(12), p.2443 - 2447, 2011/06

 Times Cited Count:2 Percentile:87.22(Physics, Condensed Matter)

Journal Articles

Sensitivity analysis for scenarios relevant to evolution of overpack and buffer material

Takeda, Seiji; Watanabe, Masatoshi; Kimura, Hideo

Proceedings of International Waste Management Symposia 2011 (WM 2011) (CD-ROM), 11 Pages, 2011/05

This study focuses on a deterioration of expected barrier functions relevant to evolution of overpack and sand-bentonite buffer material in engineered barrier system in the geological disposal of high-level radioactive waste. Release rates for important radionuclides, Cs-135 and Se-79, were estimated from Monte Carlo-based analysis for the early failure of overpack and the buffer alteration scenarios. One of the possible early failure scenarios is the change of glass dissolution rate, effective diffusion coefficients and distribution coefficients in the buffer material, which are affected by early high temperature in the engineered barrier. The analytical result indicates that this scenario has no detrimental effect on the maximum release rates of these radionuclides. Another scenario is the occurrence of the increase of Se solubility correlated with the enhanced redox potential due to the radiolysis after the early failure of overpack. This scenario allows a conspicuous increase in the maximum release rates of Se-79 from the buffer, which is over one order of magnitude higher than that in the normal scenario. In addition, with the comparison of the maximum release rates between the early failure scenario and the buffer alteration scenario, it is suggested that the effect of the deterioration of the expected barrier functions relevant to the buffer alteration on the release rates is more remarkable than the effect on early failure.

Journal Articles

Characterization of glasses for $$^{3}$$He neutron spin filter cells

Sakaguchi, Yoshifumi; Kira, Hiroshi; Oku, Takayuki; Shinohara, Takenao; Suzuki, Junichi; Sakai, Kenji; Nakamura, Mitsutaka; Suzuya, Kentaro; Arai, Masatoshi; Takeda, Masayasu; et al.

Nuclear Instruments and Methods in Physics Research A, 634(1, Suppl.), p.S122 - S125, 2011/04

Journal Articles

Incommensurate spin correlations induced by magnetic Fe ions substituted into overdoped Bi$$_{1.75}$$Pb$$_{0.35}$$Sr$$_{1.90}$$CuO$$_{6+z}$$

Hiraka, Haruhiro*; Hayashi, Yoichiro*; Wakimoto, Shuichi; Takeda, Masayasu; Kakurai, Kazuhisa; Adachi, Tadashi*; Koike, Yoji*; Yamada, Ikuya*; Miyazaki, Masanori*; Hiraishi, Masatoshi*; et al.

Physical Review B, 81(14), p.144501_1 - 144501_6, 2010/04

 Times Cited Count:14 Percentile:42.32(Materials Science, Multidisciplinary)

JAEA Reports

Assessment on long-term safety for geological disposal of high level radioactive waste; Application of probabilistic safety assessment methodology to uncertainties in hypothetical geological disposal system (Contract research)

Takeda, Seiji; Yamaguchi, Tetsuji; Nagasawa, Hirokazu; Watanabe, Masatoshi; Sekioka, Yasushi; Kanzaki, Yutaka; Sasaki, Toshihisa; Ochiai, Toru; Munakata, Masahiro; Tanaka, Tadao; et al.

JAEA-Research 2009-034, 239 Pages, 2009/11

JAEA-Research-2009-034.pdf:33.52MB

In safety assessment for geological disposal of high level radioactive waste, it is of consequence to estimate the uncertainties due to the long-term frame associated with long-lived radionuclides and the expanded geological environment. The uncertainties result from heterogeneity intrinsic to engineered and natural barrier materials, insufficient understanding of phenomena occurring in the disposal system, erroneous method of measurement, and incomplete construction. It is possible to quantify or to reduce the uncertainties according to scientific and technological progress. We applied a deterministic and a Monte Carlo-based probabilistic method simulation techniques to the uncertainty analysis for performance of hypothetical geological disposal system for high level radioactive waste. This study provides the method to evaluate the effects of the uncertainties with respect to scenarios, models and parameters in engineering barrier system on radiological consequence. The results also help us to specify prioritized models and parameters to be further studied for long-term safety assessment.

JAEA Reports

Skyshine dose calculation code system SKYOSD for operational scenario of radioactive waste disposal

Watanabe, Masatoshi; Takeda, Seiji; Kimura, Hideo

JAEA-Data/Code 2009-005, 18 Pages, 2009/06

JAEA-Data-Code-2009-005.pdf:2.79MB

The shyshine dose to the public at the site boundary of radioactive waste disposal facility has been calculated for the operational scenario which is one of the scenarios for assessing the radionuclide concentration limits for low-level radioactive wastes. The skyshine dose was calculated with the point kernel method in the previous assessment. A computer code system, SKYOSD, employs more rigorous transport equation than before. The SKYOSD stores a one-dimensional transport calculation code ANISN-JR to calculate photon fluence rate on the disposal facility, and a two-dimensional transport calculation code DOT3.5 to calculate dose from a point kernel predetermined on the facility. This report provides a description for the structure of the SKYOSD code system and the parameter setting for skyshine dose calculation.

JAEA Reports

Estimation of radioactivity concentration limit for concrete vault disposal of transuranium and uranium wastes (Contract research)

Sawaguchi, Takuma; Takeda, Seiji; Sasaki, Toshihisa; Ochiai, Toru; Watanabe, Masatoshi; Kimura, Hideo

JAEA-Research 2008-046, 62 Pages, 2008/03

JAEA-Research-2008-046.pdf:3.34MB

The Atomic Energy Commission of Japan states that the transuranium waste and uranium waste are to be disposed of by either near surface disposal without artificial barrier (trench disposal), near surface disposal with artificial barrier (concrete vault disposal), or intermediate depth disposal, depending on the radionuclides and their radioactivity concentration in the wastes. The ranges of radioactivity concentration for these different disposal concepts are, therefore, required to be determined for the regulation. The radioactivity concentration limits define the upper bound of radioactivity concentrations for licensing application of the disposal of radioactive waste. This document summaries the concept and method for estimation of the radioactivity concentration limits for concrete vault disposal of transuranium and uranium wastes, and provides the derived values of the radioactivity concentration limits for each radionuclide in the wastes.

JAEA Reports

Estimation of radioactivity concentration limit for trench disposal of transuranium and uranium wastes (Contract research)

Takeda, Seiji; Watanabe, Masatoshi; Sawaguchi, Takuma; Sasaki, Toshihisa; Ochiai, Toru; Kimura, Hideo

JAEA-Research 2008-044, 64 Pages, 2008/03

JAEA-Research-2008-044.pdf:5.21MB

This document summaries the concept and method (scenario selection, model/code description and parameter selection) for estimation of the radioactivity concentration limits for trench disposal of transuranium and uranium wastes, and provide the derived values of the radioactivity concentration limit for each radionuclide in the wastes. The values for the transuranium waste are published in a Nuclear Safety Commission of Japan report.

JAEA Reports

External effective dose conversion factors for activity concentration limit evaluation for disposal of radioactive waste (Contract research)

Sasaki, Toshihisa; Watanabe, Masatoshi; Takeda, Seiji; Sawaguchi, Takuma; Ochiai, Toru; Kimura, Hideo

JAEA-Data/Code 2008-003, 29 Pages, 2008/02

JAEA-Data-Code-2008-003.pdf:3.7MB
JAEA-Data-Code-2008-003(errata).pdf:0.04MB

In this report, external effective dose conversion factors necessary for examining the activity concentration limits are derived for three disposal concepts. After this, the activity concentration limits that constitute a permissible range of radioactive concentration to typical land disposal concept (for radioactive wastes containing transuranic nuclides from reprocessing and MOX fuel manufacturing and uranium waste from enrichment and fuel manufacturing) are calculated. External effective dose conversion factors are derived in consideration with analysis that conforms to laws that use the conversion coefficients of ICRP Publication 74 for effective dose conversion, and adoption of the latest data i.e. $$gamma$$-ray's and X-ray's energies and intensities of "JAERI-Data/Code 2001-004" as photon energy data. This document summarizes calculation method, conditions, and results of external effective dose conversion factors for transuranium and uranium wastes disposal.

JAEA Reports

External effective dose conversion factors for deriving clearance levels of uranium and transuranium wastes

Watanabe, Masatoshi; Takeda, Seiji; Kimura, Hideo

JAEA-Data/Code 2008-001, 32 Pages, 2008/02

JAEA-Data-Code-2008-001.pdf:2.05MB
JAEA-Data-Code-2008-001(errata).pdf:0.12MB

We have developed the probabilistic assessment code system (PASCLR ver.2) for derivation of clearance levels of radioactive materials for the uranium and transuranium (TRU) wastes. This code supports the dose estimation for the exposure pathways in two different scenarios; landfill disposal as industrial waste and recycle or reuse of materials. Thirty one external exposure pathways were considered in the two scenarios. The irradiation geometry for specific individuals in the external exposure pathways are divided into anteroposterior, isotoropic and rotational conditions. We employed the EGS4 code to estimate the effective dose buildup factors of these irradiation conditions for QAD-CGGP2 code. This report provides estimated values of the effective dose buildup factors, and the calculating process and the results of the external effective dose conversion factors with QAD-CGGP2 code.

68 (Records 1-20 displayed on this page)