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Yamane, Yuichi

Journal of Nuclear Science and Technology, 57(8), p.926 - 931, 2020/08

Times Cited Count：0 Percentile：100(Nuclear Science & Technology)An equation of power in subcritical quasi-steady state has been derived based on one-point kinetics equations for the purpose of utilizing it for the development of timely reactivity estimation from complicated time profile of neutron count rate. It linearly relates power, , to a new variable , which is a function of time differential of the power. It has been confirmed by using one-point kinetics code, AGNES, that the calculated points () are perfectly in a line described by the new equation and that points () calculated from transient subcritical experiments by using TRACY made a line with a slope indicated by the new equation.

Katano, Ryota; Yamanaka, Masao*; Pyeon, C. H.*

Nuclear Science and Engineering, 193(12), p.1394 - 1402, 2019/12

Times Cited Count：2 Percentile：34.3(Nuclear Science & Technology)The author proposed the linear combination method as a subcriticality measurement method which estimates the prompt neutron decay constant (alpha) correlated with the subcriticality using measurement results obtained at multiple detector positions. In this study, we conduct the pulsed neutron experiment at Kyoto University Critical Assembly (KUCA) and measure alpha by the linear combination method using measured neutron counts. Through experiment, we experimentally show that the linear combination method can reduce the higher-mode effect compared to the conventional method. In addition, experimentally show that the linear combination has capability of the different mode extraction.

Katano, Ryota

Proceedings of 27th International Conference on Nuclear Engineering (ICONE-27) (Internet), 6 Pages, 2019/05

no abstracts in English

Katano, Ryota

Nuclear Science and Engineering, 193(4), p.431 - 439, 2019/04

Times Cited Count：3 Percentile：20.8(Nuclear Science & Technology)We proposed "linear combination method" to reduce the higher order mode effect on the prompt neutron decay constant measured by the pulsed neutron experiment. When the spatial higher order mode effect is taken into account, the time evolution of the neutron counts after the pulsed neutron injection is given by linear combination of multiple exponential functions. However, the measurement results by the conventional method include the systematic error derived from the higher order mode effect because the conventional method fit the neutron counts with a single exponential function. The proposed method extract the single exponential function of the fundamental mode by linear combination of the neutron counts at multiple detectors, thus the proposed method reduces the higher order mode effect. As the verification, we applied the proposed method to the numerical simulation. The results indicate that the proposed method can reduce the higher order mode effect by linear combination.

Iwamoto, Hiroki; Nishihara, Kenji; Yagi, Takahiro*; Pyeon, C.-H.*

Journal of Nuclear Science and Technology, 54(4), p.432 - 443, 2017/04

Times Cited Count：14 Percentile：5.17(Nuclear Science & Technology)Okuno, Hiroshi; Takada, Tomoyuki

Journal of Nuclear Science and Technology, 41(4), p.481 - 492, 2004/04

Times Cited Count：0 Percentile：100(Nuclear Science & Technology)Nuclear characteristic parameters were calculated and subcriticality judgement graphs were drawn for revision purposes of the Data Collection for the Nuclear Criticality Safety Handbook. The nuclear characteristic parameters were the neutron multiplication factor in infinite media, migration area and diffusion constants for 11 kinds of typical fuels encountered in criticality safety evaluation of nuclear fuel cycle facilities. These fuels included ADU-HO, UF6-HF and Pu(NO)-UO(NO) solution, of which data were not cited in the Data Collection. The calculation was made with the Japanese evaluated nuclear data library JENDL-3.2 and a sequence of criticality calculation codes, SRAC, POST and SIMCRI. The subcriticality judgement graphs that depict the region satisfying the inequality relation of the neutron multiplication factor less than 0.98 between the two variables (a) uranium enrichment, 239Pu/Pu ratio or plutonium enrichment and (b) H/(Pu+U) ratio were drawn for the same kinds of fuels except UF6-HF in infinite media.

Okuno, Hiroshi; Ryufuku, Susumu*; Suyama, Kenya; Nomura, Yasushi; Tonoike, Kotaro; Miyoshi, Yoshinori

JAERI-Conf 2003-019, p.116 - 121, 2003/10

This paper outlines the data prepared for the 2nd version of Data Collection of the Nuclear Criticality Safety Handbook. These data are discussed in the order of its preliminary table of contents. The nuclear characteristic parameters (k, M, D) were derived, and subcriticality judgment graphs were drawn for eleven kinds of fuels which were often encountered in criticality safety evaluation of fuel cycle facilities. For calculation of criticality data, benchmark calculations using the combination of the continuous energy Monte Carlo criticality code MVP and the Japanese Evaluated Nuclear Data Library JENDL-3.2 were made. The calculation errors were evaluated for this combination. The implementation of the experimental results obtained by using NUCEF facilities into the 2nd version of the Data Collection is under discussion. Therefore, related data were just mentioned. A database is being prepared to retrieve revised data easily.

Nishihara, Kenji; Iwasaki, Tomohiko*; Udagawa, Yutaka*

Journal of Nuclear Science and Technology, 40(7), p.481 - 492, 2003/07

Times Cited Count：16 Percentile：25.97(Nuclear Science & Technology)A new one-point equation is derived according to the balance of the fission neutrons. The equation has the same form as the conventional equation containing keff. The variables of the equation are the number of the fission neutrons and the delayed neutron precursors, and the coefficients are the multiplication factors of a prompt fission neutron, a delayed neutron and a source neutron. In the equation derived here, all variables and coefficients have each clear physical meaning. Analytic, deterministic and probabilistic calculations of the equation are performed for an accelerator-driven system.

Murazaki, Minoru; Uno, Yuichi; Miyoshi, Yoshinori

JAERI-Tech 2003-029, 107 Pages, 2003/03

We have measured neutron flux distribution around the core tank of STACY heterogeneous core by position sensitive proportional counter (PSPC) to develop the method to measure reactivity for subcritical systems. The neutron flux distribution data in the position accuracy of 13mm have been obtained in the range of uranium concentration of 50g/L to 210g/L both in critical and in subcritical state. The prompt neutron decay constant, , was evaluated from the measurement data of pulsed neutron source experiments. We also calculated distribution of neutron flux and He reaction rates at the location of PSPC by using continuous energy Monte Carlo code MCNP. The measurement data was compared with the calculation results. As results of comparison, calculated values agreed generally with measurement data of PSPC with Cd cover in the region above half of solution height, but the difference between calculated value and measurement data was large in the region below half of solution height. On the other hand, calculated value agreed well with measurement data of PSPC without Cd cover.

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

Nippon Genshiryoku Gakkai-Shi, 38(11), p.907 - 911, 1996/00

Times Cited Count：0 Percentile：100(Nuclear Science & Technology)no abstracts in English

*; X.Chen*; *; Harada, Hideo*; ; Takizuka, Takakazu; Sasa, Toshinobu

Proc. of 2nd Int. Conf. on Accelerator-Driven Transmutation Technologies and Applications, 2, p.960 - 966, 1996/00

no abstracts in English

; Takizuka, Takakazu; Sasa, Toshinobu; Takada, Hiroshi; Meigo, Shinichiro

Proc. of ASMEJSME 4th Int. Conf. on Nuclear Engineering 1996 (ICONE-4), 2, p.461 - 468, 1996/00

no abstracts in English

Journal of Nuclear Science and Technology, 29(6), p.513 - 520, 1992/06

no abstracts in English

;

JAERI-M 87-057, 29 Pages, 1987/03

no abstracts in English

; ; ; M.Cho*

JAERI-M 6496, 21 Pages, 1976/03

no abstracts in English

; ; ; M.Cho*

JAERI-M 6067, 21 Pages, 1975/03

no abstracts in English

Iwamoto, Hiroki; Nishihara, Kenji; Sugawara, Takanori; Tsujimoto, Kazufumi; Sasa, Toshinobu; Maekawa, Fujio

no journal, ,