Benchmark calculations of sodium-void experiments with uranium fuels at the fast critical assembly FCA

Fukushima, Masahiro; Kitamura, Yasunori; Kugo, Teruhiko; Yamane, Tsuyoshi; Ando, Masaki; Chiba, Go; Ishikawa, Makoto; Okajima, Shigeaki

Progress in Nuclear Science and Technology (Internet), 2, p.306 - 311, 2011/10

https://doi.org/10.15669/pnst.2.306

On a fast reactor cycle scheme that incorporates a thoria-based minor actinide-containing cermet fuel

Osaka, Masahiko; Takano, Sho*; Yamane, Yoshihiro*; Misawa, Tsuyoshi*

Progress in Nuclear Energy, 50(2-6), p.212 - 218, 2008/03

https://doi.org/10.1016/j.pnucene.2007.11.002

Concept of fast reactor cycle scheme that incorporates a thoria-based minor actinide-containing cermet fuel is given. The present cermet fuel consists of oxide solid solution of Th and minor actinides and Mo inert matrix. It has been proposed as a high-performance device that can enhance minor actinide transmutation in the fast reactor cycle. It is used in an independent small cycle, whereby dedicated cycle process are adopted. Two-steps process for reprocessing of the present cermet fuel was proposed; it consists of pre-removal of Mo-inert matrix and actinide recovery. A preliminary test for pre-removal of Mo-inert matrix using surrogate cermet fuel was carried out. It was done by dissolution in nitric acid at room temperature. Results showed that Mo-inert matrix was largely dissolved, while oxide remained. Burnup characteristics of a fast reactor core loaded with the cermet fuel were investigated by using neutronic calculation codes. It was revealed that a heterogeneous composition of Mo-inert matrix in inner and outer cores could lead to effective transmutation and flattened power density. It was concluded that the present cermet fuel is potentially a promising one as a high-performance transmutation device for the fast reactor.

Measurement and analysis of breeding index in the first mock-up core (XXII-1(65V)) for water-cooled breeder reactor at FCA (Contract research)

Fukushima, Masahiro; Okajima, Shigeaki; Ando, Masaki; Yamane, Tsuyoshi; Kataoka, Masaharu*

JAERI-Research 2005-008, 57 Pages, 2005/03

JAERI-Research-2005-008.pdf:3.49MB

no abstracts in English

Reactivity estimation using digital nonlinear H estimator for VHTRC experiment

Suzuki, Katsuo; Nabeshima, Kunihiko; Yamane, Tsuyoshi; Fujii, Yoshio*

Nihon Genshiryoku Gakkai Wabun Rombunshi, 2(4), p.408 - 417, 2003/12

https://doi.org/10.3327/taesj2002.2.408

On-line and real-time estimation of time-varying reactivity in a nuclear reactor is necessary for early detection of reactivity anomaly and safe operation. Using a digital nonlinear H estimator, an experiment of real-time dynamic reactivity estimation was carried out in the VHTRC of JAERI. Some technical issues of the experiment are described, such as reactivity insertion, data sampling frequency, anti-aliasing filter, experimental circuit and digitalizing nonlinear H reactivity estimator, and so on. Then, we discussed the experimental results obtained by the digital nonlinear H estimator with sampled data of the nuclear instrumentation signal for the power responses under various reactivity insertions. Good performances of estimated reactivity were observed, with almost no delay to the true reactivity and sufficient accuracy between 0.05cent and 0.1cent. From the results of the experiment, it is concluded that the digital nonlinear H reactivity estimator can be applied as on-line real-time reactivity meter for actual nuclear plants.

Determination of reactivity and source intensity based on the maximum likelihood method

Nishihara, Kenji; Iwanaga, Kohei; Yamane, Tsuyoshi; Okajima, Shigeaki

JAERI-Research 2002-030, 63 Pages, 2002/12

JAERI-Research-2002-030.pdf:3.81MB

During the experiments using the critical assembly such that reactivity is added to the stationary state and the core shifts to the other stationary state, the neutron flux transitionally changes after some change of the reactivity or source. Inverse kinetics method (IK method) can generally adopted as the technique of obtaining the reactivity and/or source by analyzing the neutron flux. However, the conventional analysis method was not able to obtain the solution with the maximum likelihood considering the error of the measured neutron flux and to estimate the error of the solution. In the present research, by adopting the maximum likelihood methodology to the problem, developed is the technique to obtain the reactivity and source intensity with maximum likelihood and the errors of them. Moreover, the technique is applied to the rod drops experiment in FCA, and the validity of a technique is checked.

RAPID-L highly automated fast reactor concept without any control rods, 2; Critical experiment of lithium-6 used in LEM and LIM

Tsunoda, Hirokazu*; Sato, Osamu*; Okajima, Shigeaki; Yamane, Tsuyoshi; Iijima, Susumu; Kobe, Mitsuru*

Proceedings of International Congress on Advanced Nuclear Power Plants (ICAPP) (CD-ROM), 6 Pages, 2002/00

no abstracts in English

A Fortran code CVTRAN to provide cross-section file for TWODANT by using macroscopic file written by SRAC

Yamane, Tsuyoshi; *

JAERI-Data/Code 99-011, 46 Pages, 1999/03

JAERI-Data-Code-99-011.pdf:1.33MB

no abstracts in English

Weapon-grade plutonium burning with HTRs

Yamane, Tsuyoshi; Yamashita, Kiyonobu; Fujimoto, Nozomu

New approaches to the nuclear fuel cycles and related disposal schemes, 1, p.267 - 277, 1998/00

no abstracts in English

The Present active status of domestic critical assemblies and the perspective for their future, 2-4; Very high temperature reactor critical assembly (VHTRC)

Akino, Fujiyoshi; Yamane, Tsuyoshi

Nihon Genshiryoku Gakkai-Shi, 40(4), p.262 - 264, 1998/00

no abstracts in English

A Proposal of revised method for determination of large positive reactivity

Kaneko, Yoshihiko*; Shimakawa, Satoshi; Nagao, Yoshiharu; Yamashita, Kiyonobu; ; Yamane, Tsuyoshi

JAERI-Research 97-003, 70 Pages, 1997/02

JAERI-Research-97-003.pdf:1.79MB

no abstracts in English