Initialising ...
Initialising ...
Initialising ...
Initialising ...
Initialising ...
Initialising ...
Initialising ...
Urano, Hajime
JAERI-Research 2004-027, 131 Pages, 2005/02
JAERI-Research-2004-027.pdf:5.69MB
no abstracts in English
Suzuki, Satoru; Sato, Haruo
JNC TN8410 2001-028, 36 Pages, 2002/03
JNC-TN8410-2001-028.pdf:1.81MB
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.
Ikeda, Takao*; Yoshida, Hideji*
JNC TJ7400 2000-006, 159 Pages, 2000/02
JNC-TJ7400-2000-006.pdf:4.81MB
no abstracts in English
Ishikawa, Kiyoshi*; Mezaki, Yoshihiko*; Suzuki, Hideo*; Kai, Masanori*; Watanabe, Hajime*; Fujimori, Seiji*; Ishikawa, Junichi*
JNC TJ7420 99-016, 878 Pages, 1999/06
no abstracts in English
; Yamazawa, Hiromi
Journal of Nuclear Science and Technology, 34(8), p.835 - 846, 1997/08
Times Cited Count：2 Percentile：23.01(Nuclear Science & Technology)no abstracts in English
Yamamoto, Toshihiro
Nuclear Science and Engineering, 125(1), p.19 - 23, 1997/00
Times Cited Count：2 Percentile：23.01(Nuclear Science & Technology)no abstracts in English
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.
; Yamazawa, Hiromi
Journal of Nuclear Science and Technology, 32(7), p.671 - 682, 1995/07
Times Cited Count：4 Percentile：43.19(Nuclear Science & Technology)no abstracts in English
; Yamazawa, Hiromi
JAERI-Research 95-016, 22 Pages, 1995/03
JAERI-Research-95-016.pdf:0.88MB
no abstracts in English
; Yamazawa, Hiromi
JAERI-Research 94-040, 40 Pages, 1994/11
JAERI-Research-94-040.pdf:1.39MB
no abstracts in English
; Miyoshi, Yoshinori; *; *; *
Journal of Nuclear Science and Technology, 30(5), p.465 - 476, 1993/05
Times Cited Count：6 Percentile：55.9(Nuclear Science & Technology)no abstracts in English
Muramatsu, Toshiharu
PNC TN9410 90-095, 236 Pages, 1990/07
Three and two dimensional standard analytical models were to analyze in-vessel thermohydraulic phenomena of prototype fast reactor MONJU using multi-dimensional thermohydraulic analysis code AQUA. The non-structured cells, which are defined as those without solid structure inside the cell, count up tp 23270 and 2004, respectively. Pre-analysis of in-vessel natural circulation phenomena was conducted for transient simulating a pump coast down and reactor scram to a full-power operation condition (End of 10th equilibrium cycle) with the above standard models. From the analyses, the following results have been obtained: (1)Calculated flow distribution in the core on a steady-state condition agreed within the maximum error 10% and 20% compared with a design value for 3D and 2D analytical models, respectively. (2)Rising speed of thermal stratification interface predicted by the 2D analytical model was delayed for the case using the 3D model. (3)In the result using the 3D analytical model, a maximum temperature at center of a fuel pin clad not exceeded the limit value 675
C.
; ; ; Koizumi, Yasuo; Tasaka, Kanji
Proc.2nd Int.Topical Meeting on Nuclear Power Plant Thermal Hydraulics and Operations, p.1 - 102, 1986/00
no abstracts in English
; ; ; ; ; Araki, Kunio
JAERI-M 9388, 50 Pages, 1981/03
no abstracts in English
*; ; Okamoto, Yoshizo
Nihon Kikai Gakkai Rombunshu, B, 423, p.2157 - 2162, 1981/00
no abstracts in English
Tatsumi, Ryoko*; Homma, Yuki; Yamoto, Shohei*; Takahara, Keisuke*; Ishibashi, Kazuhiro*; Hatayama, Akiyoshi*
no journal, ,
no abstracts in English
