Benchmark experiments of MOX fueled LMFBR using FCA-XVII-1 core

Ando, Masaki; Iijima, Susumu*; Oigawa, Hiroyuki; Sakurai, Takeshi; Nemoto, Tatsuo*; Okajima, Shigeaki; Osugi, Toshitaka*; Ono, Akio; Hayasaka, Katsuhisa; Sodeyama, Hiroshi

JAEA-Data/Code 2006-006, 67 Pages, 2006/03

JAEA-Data-Code-2006-006.pdf:6.08MB

As a part of research and development of an advanced fueled fast reactor, we carried out benchmark experiments in the FCA-XVII-1 core with MOX simulating fuel to obtain reference data to be compared with those measured in the FCA-XVI-1 and XVI-2 cores simulating metallic fueled FBR. Following nuclear characteristics were measured in the experiments: Criticality, reaction rate ratio, sample reactivity worth, sodium void reactivity effect and U Doppler effect. Extra measurements were performed in modified FCA-XVII-1 cores to obtain experimental data for various reactor types: (1) Measurement of sodium void reactivity effect in various plutonium isotope compositions, (2) Measurement of sodium void reactivity effect in a core where axial blanket was replaced with a sodium layer and (3) Measurement of various nuclear characteristics in a nitride fuel region. This report describes methods and results of the above experiments and method of analysis.

Corrosion studies in liquid Pb-Bi alloy at JAERI; R&D program and first experimental results

Kurata, Yuji; Futakawa, Masatoshi; Kikuchi, Kenji; Saito, Shigeru; Osugi, Toshitaka

Journal of Nuclear Materials, 301(1), p.28 - 34, 2002/02

https://doi.org/10.1016/S0022-3115(01)00720-6

no abstracts in English

Critical experiment and analysis on FCA XVIII assembly

Ando, Masaki; Osugi, Toshitaka; Tsujimoto, Kazufumi

JAERI-Data/Code 98-012, 35 Pages, 1998/03

JAERI-Data-Code-98-012.pdf:1.31MB

no abstracts in English

The Present active status of domestic critical assemblies and the perspective for their future, 3; Fast critical assembly (FCA)

Osugi, Toshitaka; Okajima, Shigeaki

Nihon Genshiryoku Gakkai-Shi, 40(4), p.259 - 262, 1998/00

no abstracts in English

Research and development of nitride fuel cycle for TRU burning

; Ogawa, Toru; Osugi, Toshitaka; Arai, Yasuo; Mukaiyama, Takehiko

Proc. of 4th Int. Information Exchange Meeting on Actinide and Fission Product Partitioning and Transm, 0, p.178 - 188, 1997/00

no abstracts in English

Conceptual design study of self-completed fuel cycle system

Osugi, Toshitaka; Takano, Hideki; Ogawa, Toru; ; ; *; *; *; *

Global 1995, Int. Conf. on Evaluation of Emerging Nuclear Fuel Cycle Systems,Vol. 1, 0, p.181 - 189, 1995/00

no abstracts in English

Conceptual study of test reactor for fuel irradiation/reactor performance research

Inabe, Teruo; ; ; Yonomoto, Taisuke; *; Akutsu, Cho; ; Iwamura, Takamichi; Okubo, Tsutomu; Osugi, Toshitaka; et al.

JAERI-M 93-106, 104 Pages, 1993/05

JAERI-M-93-106.pdf:2.77MB

no abstracts in English

Measurement of power distribution in FCA-HCLWR core(Phase-1)

Ono, Akio; Osugi, Toshitaka;

JAERI-M 91-186, 63 Pages, 1991/11

JAERI-M-91-186.pdf:1.5MB

no abstracts in English

Perspectives of advanced LWR technologies

Tone, Tatsuzo; Iwamura, Takamichi; Osugi, Toshitaka; Takano, Hideki; ; Fujine, Sachio

Genshiryoku Kogyo, 37(6), p.19 - 58, 1991/06

http://ci.nii.ac.jp/naid/40001073908

no abstracts in English

Experimental study on reactivity worth for absorber material in high conversion light water reactor using FCA-HCLWR core fueled with enriched uranium

Okajima, Shigeaki; Osugi, Toshitaka; Sakurai, Takeshi; *

Journal of Nuclear Science and Technology, 27(10), p.950 - 959, 1990/10

https://doi.org/10.3327/jnst.27.950

no abstracts in English