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Journal Articles

Evaluation of impact with high temperature engineering test reactor using realistic model of stack and reactor building

Ono, Masato; Fujiwara, Yusuke; Matsumoto, Tetsuro*; Iigaki, Kazuhiko

Nihon Genshiryoku Gakkai Wabun Rombunshi, 19(2), p.110 - 120, 2020/06

Integrity confirmation for buildings against collisions of projectiles has been conducted to evaluate collisions between a projectile with simple shape and a wall using empirical formulas. It is a matter of fact, there is a possibility that structures with complex shape such as stack may collide with a reactor building. However, there were not so many studies of collisions between structures with complex shape and buildings in the literature. Impact evaluation was carried out using reactor building and stack with real shape and adequate physical property. It was found that ceiling of reactor building was not damaged by the collision, confirming that there was no effect inside of reactor building.

JAEA Reports

None

Sudo, Toshiyuki

JNC TN8200 2000-006, 443 Pages, 2000/07

JNC-TN8200-2000-006.pdf:41.45MB

None

JAEA Reports

Outline of research proposals selected in the Nuclear Energy Research Initiative (NERI) program

Iwamura, Takamichi; Okubo, Tsutomu; Usui, Shuji*; Shimada, Shoichiro*; Nabeshima, Kunihiko; ; Kakuta, Tsunemi; Ishikawa, Nobuyuki; Suzudo, Tomoaki; Nakatsuka, Toru; et al.

JAERI-Review 99-017, 60 Pages, 1999/08

JAERI-Review-99-017.pdf:2.94MB

no abstracts in English

Journal Articles

Comparison of nuclear decay data derived from recent nuclear structure data files with those of ICRP publication 38

Endo, Akira; Yamaguchi, Yasuhiro

Radiation Protection Dosimetry, 82(1), p.59 - 64, 1999/00

 Times Cited Count:2 Percentile:20.96(Environmental Sciences)

no abstracts in English

Journal Articles

Safety design requirements for nuclear fusion facilities

Inabe, Teruo

Purazuma, Kaku Yugo Gakkai-Shi, 73(8), p.812 - 819, 1997/08

no abstracts in English

JAEA Reports

Preparation of a basic data base for shielding design (II)

Takemura, Morio*

PNC TJ9055 97-001, 112 Pages, 1997/03

PNC-TJ9055-97-001.pdf:2.63MB

With use of a standard groupwise shielding design library JSSTDL produced from the latest evaluated nuclear data library JENDL-3.2, experimental analyses for the Axial Shield Experiment (homogeneous and central blockage type shield configurations with B$$_{4}$$C or stainless steel shield material) were performed. The results were compared with those obtained by the same analysis method and input data using JSDJ2 library that had been applied consistently to the JASPER experiment analyses. In general, the results with JSSTDL analyses are higher than those by JSDJ2 as were found in analyses in last year for the Radial Shield Attenuation Experiment and the Special Materials Experiment. Consideration was made on the discrepancies between JSSTDL and JSDJ2 analysis results of the Axial Shield Experiment and also those of the sodium configulation in the Radial Shield Attenuation Experiment. The former was done by exchange of macro cross section of each region, and the latter forcused on sodium cross section was done with use of cross section sensitivity analysis method. Compilation of the input data necessary for future reanalyses of important configurations in JASPER experiments, that were selected in previous study in last year, were continued and new data were added into the computer disk holding previous ones.

Journal Articles

Neutronics integral experiments of annular blanket system simulating tokamak reactor configuration

Konno, Chikara; Oyama, Yukio; Maekawa, Fujio; Ikeda, Yujiro; Kosako, Kazuaki*; Maekawa, Hiroshi; M.A.Abdou*; Bennett, E. F.*; A.Kumar*; M.Z.Youssef*

Fusion Technology, 28(2), p.347 - 365, 1995/09

no abstracts in English

Journal Articles

Neutronics integral experiments of simulated fusion reactor blanket with various beryllium configurations using Deuterium-tritium neutrons

Konno, Chikara; Oyama, Yukio; Ikeda, Yujiro; ; ; Kosako, Kazuaki*; Maekawa, Hiroshi; Nakagawa, Masayuki; Mori, Takamasa; Nakamura, Tomoo; et al.

Fusion Technology, 28(2), p.273 - 295, 1995/09

no abstracts in English

Journal Articles

Summary of benchmark experiments for simulation of fusion reactors using an annular blanket with a line deuterium-tritium source

Maekawa, Hiroshi; M.A.Abdou*; Oyama, Yukio; Konno, Chikara; Maekawa, Fujio; Ikeda, Yujiro; Kosako, Kazuaki*; Nakamura, Tomoo; M.Z.Youssef*; A.Kumar*; et al.

Fusion Technology, 28(2), p.296 - 304, 1995/09

no abstracts in English

Journal Articles

Neutronics integral experiments of lithium-oxide fusion blanket with heterogeneous configurations using deuterium-tritium neutrons

Oyama, Yukio; Konno, Chikara; Ikeda, Yujiro; ; ; Kosako, Kazuaki*; Maekawa, Hiroshi; Nakagawa, Masayuki; Mori, Takamasa; Nakamura, Tomoo; et al.

Fusion Technology, 28(1), p.216 - 235, 1995/08

no abstracts in English

Journal Articles

Design and techniques for fusion blanket neutronics experiments using an accelerator-based deuterium-tritium neutron source

Oyama, Yukio; Konno, Chikara; Ikeda, Yujiro; Maekawa, Fujio; Maekawa, Hiroshi; ; ; Nakamura, Tomoo; M.A.Abdou*; Bennett, E. F.*; et al.

Fusion Technology, 28(1), p.56 - 73, 1995/08

no abstracts in English

Journal Articles

Effect of selection of calculation parameters in discrete ordinate code DOT3.5 for analyses of fusion blanket integral experiments in JAERI-USDOE collaborative program

Oyama, Yukio; Kosako, Kazuaki*; Konno, Chikara; Ikeda, Yujiro; Maekawa, Fujio; Maekawa, Hiroshi

Fusion Engineering and Design, 28, p.636 - 641, 1995/00

no abstracts in English

Journal Articles

Summary of experiments and analyses from the JAERI/USDOE collaborative program on fusion blanket neutronics

Maekawa, Hiroshi; M.A.Abdou*

Fusion Engineering and Design, 28, p.479 - 491, 1995/00

no abstracts in English

Journal Articles

Integral experiment on effects of large opening in fusion reactor blanket on tritium breeding using annular geometry

Konno, Chikara; Oyama, Yukio; Maekawa, Fujio; Ikeda, Yujiro; Kosako, Kazuaki*; Maekawa, Hiroshi; M.A.Abdou*; A.Kumar*; M.Z.Youssef*

Fusion Engineering and Design, 28, p.708 - 715, 1995/00

no abstracts in English

Journal Articles

Summary of benchmark experiments for simulation of fusion reactors using an annular blanket with a line D-T source

Maekawa, Hiroshi; Oyama, Yukio; M.A.Abdou*

Materials for Advanced Energy Systems & Fission and Fusion Engineering '94, 0, p.235 - 246, 1994/00

no abstracts in English

Journal Articles

JAERI/USDOE collaborative experiments on fusion blanket neutronics

Oyama, Yukio

NCC Nyusu, 0(18), p.17 - 23, 1994/00

no abstracts in English

Journal Articles

Effect of neutron irradiation on deformation behavior in TiPd-Cr high temperature shape memory alloys

Hoshiya, Taiji; Goto, Ichiro; Omi, Masao; Ando, Hiroei; ;

Shape Memory Materials and Hydrides (Trans. of Materials Research Soc. Jpn., Vol. 18B), 0, p.1025 - 1028, 1994/00

no abstracts in English

Journal Articles

Deformation behavior of TiPd-Cr high temperature shape memory alloys

Hoshiya, Taiji; ;

Shape Memory Materials and Hydrides (Trans. of Materials Research Soc. Jpn., Vol. 18B), 0, p.1013 - 1016, 1994/00

no abstracts in English

JAEA Reports

Phase IIC experiments of the USDOE/JAERI collaborative program on fusion blanket neutronics; Experiments and analysis of heterogeneous fusion blankets, Volume II: Analysis

Nakagawa, Masayuki; Kosako, Kazuaki*; Mori, Takamasa; Oyama, Yukio; Konno, Chikara; Ikeda, Yujiro; Yamaguchi, Seiya*; Tsuda, Koichi*; Maekawa, Hiroshi; ; et al.

JAERI-M 92-183, 106 Pages, 1992/12

JAERI-M-92-183.pdf:2.6MB

no abstracts in English

JAEA Reports

Phase IIC experiments of the JAERI/USDOE collaborative program on fusion blanket neutronics; Experiments and analysis of the heterogeneous fusion blankets, Volume I: Experimental results

Oyama, Yukio; Konno, Chikara; Ikeda, Yujiro; Yamaguchi, Seiya*; Tsuda, Koichi*; Maekawa, Hiroshi; ; Kosako, Kazuaki*; Nakagawa, Masayuki; Mori, Takamasa; et al.

JAERI-M 92-182, 151 Pages, 1992/12

JAERI-M-92-182.pdf:4.31MB

no abstracts in English

32 (Records 1-20 displayed on this page)