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Suzuki, Satoru; Sato, Haruo
JNC TN8410 2001-028, 36 Pages, 2002/03
For a safety assessment of the high-level radioactive waste disposal, effective diffusion coefficients (D) of radionuclides in bentonite have been accumulated by the through-diffusion method. It has been found recently that experimental results on Ds for several cations (cesium and strontium) by the fairly standard experimental method in JNC differ from those previously reported in several papers. Discrepancy can be considered to be due to different design of diffusion cell and system. In order to confirm influences of the experimental design on cation diffusivities in bentonite, a flow-through diffusion system was developed and several diffusion experiments were conducted.As a result, magnitude of D and its salinity dependence were relatively different between the standard and flow-through diffusion system. Since the latter system can control boundary conditions of the experiment more strictly than the standard method, we can conclude that the flow-through diffusion system provide correct results. In addition, we apply this flow-through diffusion system to a modification of controlling boundary condition during the experiment and to the diffusion experiment under controlled temperature.
Yamauchi, Toshihiko
Kankyo Kagakkai-Shi, 14(6), p.567 - 575, 2001/12
no abstracts in English
Kitajima, Toshio; Abe, Shinichi; Takahashi, Kiyoshi; Onuma, Yuichi; Watanabe, Hiroyuki; Okada, Yuji; Oyake, Noriyuki*
UTNL-R-0404, p.6_1 - 6_9, 2001/00
no abstracts in English
Yamada, Tadanori; ; Shirasu, Noriko
JAERI-Tech 97-072, 32 Pages, 1998/01
no abstracts in English
Ugolini; Yoshikawa, Shinji; Ozawa, Kenji
PNC TN9410 95-253, 13 Pages, 1995/10
This report presents the implementation of the a model reference adaptive control system based on the artificial neural network technique (MRAC) in a fast breeder reactor (FBR) building block type (BBT) simulator representing the Monju prototype reactor. The purpose of this report is to improve the control of the outlet steam temperature of the three evaporators of the Monju prototype reactor. The connection between the MRAC system and the BBT simulator is achieved through an external shared memory accessible by both systems. The MRAC system calculates the demand for the position of the feedwater valve replacing the signal of a PID controller collocated inside the heat transport system model of the Monju prototype reactor. Two series of simulation tests havc been performed, one with one loop connected to the MRAC system (leaving the remaining two connected to the original PID controller), and the other with three loops connected to the MRAC system. In both simulation tests the MRAC system performed better than the PID controller, keeping the outlet steam temperature of the evaporators closer to the required set point value through all the transients.
Ugolini; Yoshikawa, Shinji; Ozawa, Kenji
PNC TN9410 95-210, 11 Pages, 1995/09
The proper control of the outlet steam temperature of the evaporator is of major importance for improving the overall performance of the balance of plant of a nuclear power reactor. This report presents a predictive and an anticipatory control algorithms based on the artificial neural network (ANN) technique. The two control algorithms are embedded on a model reference adaptive control system based on the ANN technique, defined as MRAC. It has already been illustrated that nonlinear dynamical systems such as the evaporator of a nuclear power plant can be controlled by an MRAC system. However, little attention has been devoted on exploiting the forecasting potential of the ANN technique for enhancing the accuracy and improving the efficacy of the control action of the MRAC system. The improved MRAC system has been tested to simulate the behavior of a fast breeder reactor (FBR) evaporator and to control its outlet steam temperature. The simulation results indicate that the performance of the MRAC system substantially improves when the predictive and the anticipatory control algorithms are activated.
; Uramoto, Toshimasa; Fukushima, Masao; ; ; ;
Proc. of the 3rd Asian Symp. on Research Reactor, p.285 - 292, 1991/00
no abstracts in English
; Endo, Yasuichi; ;
UTNL-R-0247, 6 Pages, 1990/00
no abstracts in English
; ; ; *; Okamoto, Yoshizo
JAERI-M 86-162, 47 Pages, 1986/09
no abstracts in English
*; Tone, Tatsuzo
JAERI-M 85-203, 35 Pages, 1985/12
no abstracts in English
; Ito, Hiroshi; ; Katakai, Akio; Hagiwara, Miyuki; Araki, Kunio
JAERI-M 8183, 87 Pages, 1979/03
no abstracts in English
; Yoshida, Kenzo; ; ; Araki, Kunio
JAERI-M 6593, 34 Pages, 1976/06
no abstracts in English