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Journal Articles

Recalibration test of dump tank at NUCEF

Ono, Akio*

Kaku Busshitsu Kanri Senta Nyusu, 33(9), p.12 - 15, 2004/09

no abstracts in English

JAEA Reports

A Kinetics code for criticality accident analysis of fissile solution systems: AGNES2

Nakajima, Ken; Yamane, Yuichi; Miyoshi, Yoshinori

JAERI-Data/Code 2002-004, 42 Pages, 2002/03

JAERI-Data-Code-2002-004.pdf:1.51MB

no abstracts in English

Journal Articles

Source term on release behavior of radioactive materials from fuel solution under simulated nuclear criticality accident

Abe, Hitoshi; Tashiro, Shinsuke; Koike, Tadao; Okagawa, Seigo; Uchiyama, Gunzo

Proceedings of the 2001 Topical Meeting on Practical Implementation of Nuclear Criticality Safety (CD-ROM), 8 Pages, 2001/11

no abstracts in English

JAEA Reports

Studies on release behavior of radioactive noble gases from fuel solution to gas phase under simulated nuclear criticality accident (Contract research)

Abe, Hitoshi; Tashiro, Shinsuke; Koike, Tadao; Okagawa, Seigo; Uchiyama, Gunzo

JAERI-Research 2001-027, 20 Pages, 2001/03

JAERI-Research-2001-027.pdf:1.0MB

no abstracts in English

JAEA Reports

Annual report of STACY operation in F.Y. 1998, 2; 800mm-diameter cylindrical core$$cdot$$10% enriched uranyl nitrate solution (Contract research)

Onodera, Seiji; Sono, Hiroki; Hirose, Hideyuki; Tanino, Shuichi; Nagasawa, Makoto*; Murakami, Kiyonobu; Sakuraba, Koichi; Miyauchi, Masakatsu; Yamane, Yuichi; Ono, Akio

JAERI-Tech 2000-013, p.57 - 0, 2000/03

JAERI-Tech-2000-013.pdf:2.43MB

no abstracts in English

Journal Articles

An Accident at conversion facility for nuclear fuel materials and education on safety culture

Obata, Masahiro

Semina Tsushin, (21), p.13 - 14, 2000/03

no abstracts in English

JAEA Reports

Study on the release behavior of radioactive iodine spices and noble gases from the fuel solution under simulated nuclear criticality accident (Contract research)

Abe, Hitoshi; Tashiro, Shinsuke; Nagai, Hitoshi; Koike, Tadao; Okagawa, Seigo; Murata, Mikio

JAERI-Tech 99-067, p.23 - 0, 1999/09

JAERI-Tech-99-067.pdf:1.37MB

no abstracts in English

Journal Articles

Current status of criticality safety experiment in NUCEF and its enhancement of facility function toward Pu experiment

Takeshita, Isao; Ono, Akio; Izawa, Naoki*; Miyoshi, Yoshinori; Maeda, Atsushi; Sugikawa, Susumu; Miyauchi, Masakatsu

Proceedings of 6th International Conference on Nuclear Criticality Safety (ICNC '99), p.1512 - 1576, 1999/09

no abstracts in English

JAEA Reports

Improvement of fuel sampling device for STACY and TRACY

Hirose, Hideyuki; Sakuraba, Koichi; ; ; *; *; ; ; ; Miyauchi, Masakatsu; et al.

JAERI-Tech 98-015, 52 Pages, 1998/05

JAERI-Tech-98-015.pdf:1.68MB

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

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

Most critical geometry of a fuel solution based on the transport boundary perturbation theory

Yamamoto, Toshihiro

Journal of Nuclear Science and Technology, 33(1), p.78 - 82, 1996/01

 Times Cited Count:1 Percentile:14.44(Nuclear Science & Technology)

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

Application of time-dependent boundary-fitted curvilinear coordinate system for kinetic analysis of aqueous fuel solution sloshing behaviour

Yamamoto, Toshihiro

Nucl. Eng. Des., 154(2), p.145 - 155, 1995/03

 Times Cited Count:1 Percentile:17.53(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Estimation of scale of criticality accident by simplified evaluation models

Nomura, Yasushi; Okuno, Hiroshi

Nihon Genshiryoku Gakkai-Shi, 35(2), p.155 - 163, 1993/02

no abstracts in English

JAEA Reports

Mock-up apparatus for preparation of plutonium fuel solution for criticality experiments at NUCEF

Sakurai, Satoshi; Hirata, Masaru; ; Usuda, Shigekazu; Abe, Jiro; ; Tachimori, Shoichi; ; Kurihara, Masayoshi; Kobayashi, Iwao

JAERI-M 90-059, 35 Pages, 1990/03

JAERI-M-90-059.pdf:1.38MB

no abstracts in English

24 (Records 1-20 displayed on this page)