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Journal Articles

Neutron resonance absorption imaging of simulated high-level radioactive waste in borosilicate glass

Oba, Yojiro; Motokawa, Ryuhei; Kaneko, Koji; Nagai, Takayuki; Tsuchikawa, Yusuke; Shinohara, Takenao; Parker, J. D.*; Okamoto, Yoshihiro

Scientific Reports (Internet), 13, p.10071_1 - 10071_8, 2023/06

 Times Cited Count:1 Percentile:72.91(Multidisciplinary Sciences)

Journal Articles

Nanoscopic structure of borosilicate glass with additives for nuclear waste vitrification

Motokawa, Ryuhei; Kaneko, Koji; Oba, Yojiro; Nagai, Takayuki; Okamoto, Yoshihiro; Kobayashi, Taishi*; Kumada, Takayuki; Heller, W. T.*

Journal of Non-Crystalline Solids, 578, p.121352_1 - 121352_7, 2022/02

 Times Cited Count:3 Percentile:22.84(Materials Science, Ceramics)

Journal Articles

Study of the applicability of CFD calculation for HTTR reactor

Tsuji, Nobumasa*; Nakano, Masaaki*; Takada, Eiji*; Tokuhara, Kazumi*; Ohashi, Kazutaka*; Okamoto, Futoshi*; Tazawa, Yujiro; Inaba, Yoshitomo; Tachibana, Yukio

Proceedings of 6th International Topical Meeting on High Temperature Reactor Technology (HTR 2012) (USB Flash Drive), 9 Pages, 2012/10

Passive heat removal performance of the reactor vessel cavity cooling system (RCCS) is of primary concern for enhanced inherent safety of HTGR. In a loss of forced cooling accident, decay heat must be removed by radiation and natural convection of RCCS. Thus thermal hydraulic analysis of reactor internals and RCCS is powerful means for evaluation of the heat removal performance of RCCS. The thermal hydraulic analyses using CFD computation tools are conducted for normal operation of the High Temperature Engineering Test Reactor (HTTR) and are compared to the temperature distribution of measured data. The calculated temperatures on outer faces of the permanent side reflector (PSR) blocks are in fair agreement with measured data. The transient analysis for decay heat removal mode in HTTR is also conducted.

Journal Articles

Core design and safety analyses of 600 MWt, 950$$^{circ}$$C high temperature gas-cooled reactor

Nakano, Masaaki*; Takada, Eiji*; Tsuji, Nobumasa*; Tokuhara, Kazumi*; Ohashi, Kazutaka*; Okamoto, Futoshi*; Tazawa, Yujiro; Tachibana, Yukio

Proceedings of 6th International Topical Meeting on High Temperature Reactor Technology (HTR 2012) (USB Flash Drive), 6 Pages, 2012/10

The conceptual core design study of High Temperature Gas-cooled Reactor (HTGR) is performed. The major specifications are 600 MW thermal output, 950$$^{circ}$$C outlet coolant temperature, prismatic core type, enriched uranium fuel. The decay heat in the core can be removed with only passive measures, for example, natural convection reactor cavity cooling system (RCCS), even if any electricity is not supplied (station blackout). The transient thermal analysis of the depressurization accident in the case the primary coolant decreases to the atmosphere pressure shows that the fuels and the reactor pressure vessel temperatures are kept under their safety limit criteria. The fission product release, $$^{rm 110m}$$Ag and $$^{137}$$Cs from the fuels under the normal operation is small as to make maintenance of devices in the primary cooling system, such as a gas turbine, without remote maintenance. The HTGRs can achieve the advanced safety features based on their inherent passive safety characteristics.

Journal Articles

Conceptual core design study of the Very High Temperature gas-cooled Reactor (VHTR); Upgrading the core performance by using multihole-type fuel

Ohashi, Kazutaka; Nishihara, Tetsuo; Kunitomi, Kazuhiko; Nakano, Masaaki*; Tazawa, Yujiro*; Okamoto, Futoshi*

Nihon Genshiryoku Gakkai Wabun Rombunshi, 7(1), p.32 - 43, 2008/03

Interests on the development of the Very High-Temperature Gas-Cooled Reactor (VHTR), of which the reactor outlet temperature is 950$$^{circ}$$C or much higher, are recently increasing world-widely and it was selected as one of the candidate reactor types of the GIF. Japan Atomic Energy Agency has already initiated R&D efforts on the electricity and hydrogen co-generation plant with VHTR system, GTHTR300C. Although technical feasibility of its VHTR reactor using Pin-in-block fuel, which has experience to be already used in the HTTR, has been shown fundamentally, more improvements of the core performances, such as decrease of the occupational exposure doses during the plant maintenance, are desired. This report presents the results of the conceptual core design study using Multi-hole type fuel and the study on the occupational exposure doses. The latter results shows much better plant maintainability compared to the previous results of the GTHTR-300.

Journal Articles

Characteristics of alanine dosimeter under low dose-rate and long time irradiation; Residual life estimation of organic materials used in the radiation environment

Haruyama, Yasuyuki; Tachibana, Hiroyuki; Kojima, Takuji; *; Kashiwazaki, Shigeru*; *; *

Radioisotopes, 44(8), p.507 - 513, 1995/08

no abstracts in English

Journal Articles

Application of dyed PVA films to 150-300keV electron beam dosimetry

W.H.Chung*; Kojima, Takuji; *

Radioisotopes, 43(5), p.278 - 282, 1994/05

no abstracts in English

Journal Articles

Development of alanine dose-reader

Haruyama, Yasuyuki; Kojima, Takuji; Tachibana, Hiroyuki; Agematsu, Takashi; Okamoto, Jiro; *

Radioisotopes, 42(8), p.445 - 451, 1993/08

no abstracts in English

JAEA Reports

The Specification and the operation characteristics of the low energy accelerator in JAERI-TRCRE

Haruyama, Yasuyuki; Yotsumoto, Keiichi; Okamoto, Jiro

JAERI-M 93-114, 46 Pages, 1993/06

JAERI-M-93-114.pdf:1.45MB

no abstracts in English

Journal Articles

Development of portable ESR spectrometer as a reader for alanine dosimeters

Kojima, Takuji; Haruyama, Yasuyuki; Tachibana, Hiroyuki; Tanaka, Ryuichi; Okamoto, Jiro; *; *

Applied Radiation and Isotopes, 44(1-2), p.361 - 365, 1993/00

 Times Cited Count:5 Percentile:50.63(Chemistry, Inorganic & Nuclear)

no abstracts in English

Journal Articles

Study on dosimetry of bremsstrahlung radiation processing

Sunaga, Hiromi; Tachibana, Hiroyuki; Tanaka, Ryuichi; Okamoto, Jiro; *; Saito, Toshio*

Radiation Physics and Chemistry, 42(4-6), p.749 - 752, 1993/00

 Times Cited Count:3 Percentile:38.1(Chemistry, Physical)

no abstracts in English

Journal Articles

Recent progress in JAERI alanine/ESR dosimeter system

Kojima, Takuji; Tachibana, Hiroyuki; Haruyama, Yasuyuki; Tanaka, Ryuichi; Okamoto, Jiro

Radiation Physics and Chemistry, 42(4-6), p.813 - 816, 1993/00

 Times Cited Count:8 Percentile:63.68(Chemistry, Physical)

no abstracts in English

Journal Articles

Alanine/ESR dosimetry system for routine use in radiation processing

Kojima, Takuji; Haruyama, Yasuyuki; Tachibana, Hiroyuki; Tanaka, Ryuichi; Okamoto, Jiro; *; *; *; Kashiwazaki, Shigeru*

Radiation Physics and Chemistry, 42(4-6), p.757 - 760, 1993/00

 Times Cited Count:7 Percentile:60.43(Chemistry, Physical)

no abstracts in English

Journal Articles

Outline of positron factory project in Japan

Okada, Sohei; Sunaga, Hiromi; Kaneko, Hirohisa; Tachibana, Hiroyuki; Yotsumoto, Keiichi; Okamoto, Jiro

Hoshasen, 18(2), p.63 - 81, 1992/05

no abstracts in English

Journal Articles

Investigation on the positron factory project at JAERI, V; Technical investigation of a high-power electron linac

Sunaga, Hiromi; Okada, Sohei; Kaneko, Hirohisa; Tachibana, Hiroyuki; Yotsumoto, Keiichi; Okamoto, Jiro

Proc. of the 17th Linear Accelerator Meeting in Japan, p.124 - 126, 1992/00

no abstracts in English

Journal Articles

Investigation on the Positron Factory Project at JAERI, IV; Technical survey of electron linac for the positron factory

Sunaga, Hiromi; Okada, Sohei; Tachibana, Hiroyuki; Yotsumoto, Keiichi; Okamoto, Jiro

Proc. of the 16th LINEAR Accelerator Meeting in Japan, p.112 - 114, 1991/00

no abstracts in English

Journal Articles

The Synthesis of a new type adsorbent for the removal of toxic gas by radiation-induced graft polymerization

Okamoto, Jiro; Sugo, Takanobu; *; *

Radiation Physics and Chemistry, 35(1-3), p.113 - 116, 1990/00

no abstracts in English

Journal Articles

Development of fibrous adsorbents by radiation graft polymerization

Okamoto, Jiro

Kagaku Keizai, 1989(1), p.88 - 95, 1989/01

no abstracts in English

Journal Articles

Transport of metal ions through chelating membrane containing amidoxime group

Sugo, Takanobu; Okamoto, Jiro

Nihon Kagakkai-Shi, 1988(9), p.1601 - 1606, 1988/09

no abstracts in English

Journal Articles

Performance of fixed-bed charged with chelating resin of capillary fiber form for recovery of uranium from seawater

Uezu, Kazuya*; Saito, Kyoichi*; Hori, Takahiro*; Furusaki, Shintaro*; Sugo, Takanobu; Okamoto, Joro

Nihon Genshiryoku Gakkai-Shi, 30(4), p.359 - 364, 1988/04

 Times Cited Count:7 Percentile:61.33(Nuclear Science & Technology)

no abstracts in English

117 (Records 1-20 displayed on this page)