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JAEA Reports

Construction of STACY(Static Experiment Critical Facility)

Murakami, Kiyonobu; ; Hirose, Hideyuki; ; *; *; Sakuraba, Koichi; ; ; *; et al.

JAERI-Tech 98-033, 70 Pages, 1998/08

JAERI-Tech-98-033.pdf:2.25MB

no abstracts in English

Journal Articles

Review of the STACY & TRACY experiment programs since their first criticality

Tonoike, Kotaro; Nakajima, Ken; Miyoshi, Yoshinori; Izawa, Naoki; Ono, Akio; Okazaki, Shuji; Takeshita, Isao

Proc. of 5th Int. Nucl. Conf. on Recycling, Conditioning and Disposal (RECOD '98), 1, p.54 - 61, 1998/00

no abstracts in English

Journal Articles

Present status and prospects of NUCEF project; Fuel cycle safety engineering research

Takeshita, Isao; Maeda, Mitsuru; Miyoshi, Yoshinori; Ono, Akio; Okazaki, Shuji; Nakajima, Ken; Fujine, Sachio; Kubota, Masumitsu; Muraoka, Susumu; Ara, Katsuyuki; et al.

Genshiryoku Kogyo, 43(9), p.1 - 37, 1997/09

no abstracts in English

Journal Articles

Critical experiments on 10% enriched uranyl nitrate solution using a 60-cm-diameter cylindrical core

Miyoshi, Yoshinori; ; Tonoike, Kotaro; Izawa, Naoki; Sugikawa, Susumu; Okazaki, Shuji

Nuclear Technology, 118(1), p.69 - 82, 1997/04

 Times Cited Count:13 Percentile:70.37(Nuclear Science & Technology)

no abstracts in English

JAEA Reports

Seismic design of reactors in NUCEF

*; *; *; *; ; Sakuraba, Koichi; Izawa, Naoki; Takeshita, Isao

JAERI-Tech 97-010, 276 Pages, 1997/03

JAERI-Tech-97-010.pdf:8.45MB

no abstracts in English

JAEA Reports

Outline of a fuel treatment facility in NUCEF

Sugikawa, Susumu; ; ; Nakazaki, Masato; Shirahashi, Koichi; ; *; *; Tsuji, Kenichi*; Tachimori, Shoichi; et al.

JAERI-Tech 97-007, 86 Pages, 1997/03

JAERI-Tech-97-007.pdf:3.27MB

no abstracts in English

JAEA Reports

Annual report of STACY in 1995; 600mm diameter cylindrical core and 10% enriched uranyl nitrate solution

; ; Hirose, Hideyuki; *; *; Ono, Akio; Sakuraba, Koichi; Izawa, Naoki; Tonoike, Kotaro; *; et al.

JAERI-Tech 97-005, 107 Pages, 1997/03

JAERI-Tech-97-005.pdf:3.26MB

no abstracts in English

JAEA Reports

Design, construction and tests of geometrically safe mixer settler

; Sugikawa, Susumu; ; Miyoshi, Yoshinori; Miyauchi, Masakatsu; Izawa, Naoki

JAERI-Tech 96-058, 28 Pages, 1997/01

JAERI-Tech-96-058.pdf:1.21MB

no abstracts in English

Journal Articles

Outline and operational experience of the fuel treatment system for criticality safety experiments in NUCEF

; Sugikawa, Susumu; Miyauchi, Masakatsu; Okazaki, Shuji; Izawa, Naoki

Proceedings of ENS Class 1 Topical Meeting; Research Facilities for the Future of Nuclear Energy, 0, p.322 - 329, 1996/00

no abstracts in English

Journal Articles

New critical assemblies- STACY/TRACY

Izawa, Naoki

Radioisotopes, 45(7), p.479 - 480, 1996/00

no abstracts in English

JAEA Reports

Dissolution of uranium with the fuel treatment system of NUCEF

; *; Sugikawa, Susumu; Izawa, Naoki

JAERI-Tech 95-038, 44 Pages, 1995/07

JAERI-Tech-95-038.pdf:1.07MB

no abstracts in English

Journal Articles

Construction of new critical experiment facilities in JAERI

Takeshita, Isao; ; ; Tonoike, Kotaro; ; Miyoshi, Yoshinori; Nakajima, Ken; Izawa, Naoki

3rd JSME/ASME Joint Int. Conf. on Nuclear Engineering (ICONE), 4, p.1881 - 1886, 1995/00

no abstracts in English

Journal Articles

New critical facilities toward their first criticality, STACY and TRACY in NUCEF

Tonoike, Kotaro; Izawa, Naoki; Okazaki, Shuji; Sugikawa, Susumu; Takeshita, Isao; *

ICNC 95: 5th Int. Conf. on Nuclear Criticality Safety,Vol. II, 0, p.10.25 - 10.32, 1995/00

no abstracts in English

Journal Articles

Nearing completion of NUCEF construction; Present status and prospects of NUCEF project

Tsujino, Takeshi; Naito, Yoshitaka; Maeda, Mitsuru; ; Hoshi, Michio; Izawa, Naoki; Takeshita, Isao; ; Okazaki, Shuji; Dojiri, Shigeru

Genshiryoku Kogyo, 40(5), p.9 - 59, 1994/00

no abstracts in English

Journal Articles

Safety research programs in NUCEF for fuel cycle back-end facilities

Tsujino, Takeshi; Takeshita, Isao; Izawa, Naoki;

Topical meeting,Safety of the Nuclear Fuel Cycle, 0, p.124 - 137, 1994/00

no abstracts in English

Journal Articles

Safety design of the NUCEF critical facilities

Takeshita, Isao; Nomura, Masayuki; ; Izawa, Naoki; Yanagisawa, Hiroshi

Proc. of the 3rd Int. Conf. on Nuclear Fuel Reprocessing and Waste Management,Vol. 1, p.510 - 515, 1991/00

no abstracts in English

Journal Articles

Experimental studies on thermal and hydraulic performance of fuel stack on VHTR, IV; Test results of HENDEL single-channel test rig when helium gas was heated up to 1000$$^{circ}$$C

Hino, Ryutaro; Takase, Kazuyuki; Maruyama, So; Izawa, Naoki; ; Shimomura, Hiroaki;

Nihon Genshiryoku Gakkai-Shi, 30(4), p.343 - 349, 1988/00

 Times Cited Count:1 Percentile:19.68(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Sudies on thermal and hydraulic performance of fuel stack of VHTR, Part III; Experimental and analytical results of HENDEL multi-channel test rig with 12 independently heated fuel rods

; ; ; ; ;

Nihon Genshiryoku Gakkai-Shi, 29(2), p.133 - 140, 1987/02

 Times Cited Count:1 Percentile:19.35(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Experimental studies on the thermal and hydraulic performance of the fuel stack of the VHTR, Part I; HENDEL single-channel tests with uniform heat flux

; ; ; ; ;

Nucl.Eng.Des., 102, p.1 - 9, 1987/00

 Times Cited Count:9 Percentile:66.68(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Experimental studies on the thermal and hydraulic performance of the fuel stack of the VHTR, Part II; HENDEL multi-channel test rig with twelve fuel rods

; ; ; ; ;

Nucl.Eng.Des., 102, p.11 - 20, 1987/00

 Times Cited Count:5 Percentile:50.76(Nuclear Science & Technology)

no abstracts in English

34 (Records 1-20 displayed on this page)