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Journal Articles

Design method of discrete-time 2DOF controller based on output response sequence; Suppression of manipulated variable oscillation by regularized least square solution

Ishikawa, Nobuyuki; Abe, Kenichi*

Denki Gakkai Rombunshi, C, 124(2), p.580 - 581, 2004/02

We have previously proposed the method for designing feedforward element of discrete-time 2DOF controller to realize a desired output response (reference response characteristics). In the method, the feedforward element is designed in the least square sense by solving a linear equation expressing the relation between the output sequence and the design parameter of feedforward element. Since this method is based on the controller parameterized by stable rational function, it is possible to realize desired reference response characteristics approximately even for the non-minimum phase plant by setting the rational function parameter to the polynomial. In this report, the design result by regularized least square solution is presented to suppress the manipulated variable response oscillation especially caused in the case for the non-minimum phase plant.

JAEA Reports

Passive electromagnetic NED for mechanical damage inspection by detecting leakage magnetic flux, 1; Reconstruction of magnetic charges from detected field signals

; Aoto, Kazumi;

JNC TN9400 99-061, 32 Pages, 1999/07

JNC-TN9400-99-061.pdf:0.95MB

In this report, reconstruction of magnetic charges induced by mechanical damages in a test piece of SUS304 stainless steel is performed as a part of eforts to establish a passive nondestructive testing method on the basis of the inspection of leakage magnetic field. The approach for solving this typical ill-posed inverse problem is selected as a way in the least square method category. Concerning the ill-poseness of the system of equations, an iteration algorithm is adopted to its solving in which the designations of initial profile, the weight coefficients and the total number of iterations are taken as means of reqularization. From examples using simulated input data, it is verified that the approach gives good reconstruction results in case of signals with a relative high S/N ratio. For improving the robustness of the proposed method, a Galerkin procedure with base functions chosen as the Daubechies' wavelet is also introduced for discretizing the governing equation. By comparing the reconstruction results of the least square method and those using wavelet discretization, it is found that the wavelet used approach is more feasible in the inversion of noise polluted signals. Reconstruction of 1-D and 2-D magnetic charges with the least square strategy and reconstruction of an 1-D problem with the wavelet used method are carried out from both simulated and measured magnetic field signals which are used as the validation of the proposed inversion strategy.

JAEA Reports

Thermal conductivity of beginning-of-life uranium-plutonium mixed oxide fuel for fast reactor (Secondary report)

;

JNC TN9400 98-005, 40 Pages, 1998/11

JNC-TN9400-98-005.pdf:2.39MB

Thermal conductivity of uranium-plutonium mixed oxide fuel for fast reactor at beginning-of-life was re-correlated in order to apply to the fuel design and the fuel pin performance analysis. Thermal conductivity of actual fuel with porosity ($$lambda$$), that of fully dense fuel ($$lambda$$$$_{0}$$) and porosity correction factor (F) has theoretically the following correlation : $$lambda$$ = F$$lambda$$$$_{0}$$, The database (221 points) were selected by adopting following criteria: "validated by different authors and methods" and "high density fuel specimens around 95% of theoretical density". The database were corrected to fully dense condition by modified Loeb equation : F=1-2.5P (P: fractional porosity) and then correlated by the least square method program. The electron conduction term of uranium dioxide reported by Harding was used in order to compensate for the lack of the high temperature range data. New correlation for fully dense fuel was developed again and shown below, which the data base used in the analysis ranged from 20 to 30% for plutonium content in heavy metal atoms, 1.98 and 2.00 for oxygen to metal ratio, from 94.3 to 96.4% of theoretical density and from 64 to 2279$$^{circ}$$C for temperature. $$lambda$$$$_{0}$$ = $$frac{1}{0.06059+0.2754 sqrt{2-O/M}+2.011times 10^{-4}T}$$ +$$frac{4.715 times 10^9} {T^{2}}$$ exp($$frac{-16361}{T}$$) where...$$lambda$$$$_{0}$$: Thermal conductivity of fully dense MOX fuel for fast reactor (W/mK). T: Temperature (K). O/M: Oxygen-to-metal ratio (-). The above correlation could be applied for fully dense and typical MOX fuel pellet of fast reactor ranging from room temperature up to melting point.

Journal Articles

Decomposition of prompt $$gamma$$-ray spectra including the Doppler-broadened peak for boron determination

Magara, Masaaki; Yonezawa, Chushiro

Nuclear Instruments and Methods in Physics Research A, 411(1), p.130 - 136, 1998/00

 Times Cited Count:24 Percentile:85.13(Instruments & Instrumentation)

no abstracts in English

JAEA Reports

Covariance evaluation system

Kawano, Toshihiko*; Shibata, Keiichi

JAERI-Data/Code 97-037, 47 Pages, 1997/09

JAERI-Data-Code-97-037.pdf:1.92MB

no abstracts in English

Journal Articles

Impacts of data transformations on least-squares solutions and their significance in data analysis and evaluation

Chiba, Satoshi; D.L.Smith*

Journal of Nuclear Science and Technology, 31(8), p.770 - 781, 1994/08

 Times Cited Count:14 Percentile:75.32(Nuclear Science & Technology)

no abstracts in English

JAEA Reports

None

PNC TJ1632 94-001, 91 Pages, 1994/03

PNC-TJ1632-94-001.pdf:2.37MB

no abstracts in English

Journal Articles

An Analysis method of gamma-ray pulse-height distributions obtained with a Ge(Li) detector

; ;

Nuclear Instruments and Methods, 125(4), p.507 - 523, 1975/04

no abstracts in English

JAEA Reports

JAEA Reports

JAEA Reports

A Study on Analysis of Gamma-Ray Spectra by Ge(Li) Detector

; ;

JAERI-M 5556, 44 Pages, 1974/02

JAERI-M-5556.pdf:1.33MB

no abstracts in English

JAEA Reports

Oral presentation

Quantitative analysis and LIBS spectra analysis using the least-squares method

Akaoka, Katsuaki; Oba, Masaki; Miyabe, Masabumi; Wakaida, Ikuo

no journal, , 

For quantitative analysis of the mixed oxide (MOX) fuel using Laser Induced Breakdown Spectroscopy (LIBS), great deal of analysis and identification of spectra are necessary. Therefore, we tried "the analysis of the LIBS spectrum by the least-squares method" as quantitative analysis without identification and analysis of the spectra. As a result, the calibration curves for quantitative analysis could be got without them.

Oral presentation

Development of quick and remote analysis for severe accident reactor, 5; Analysis of spectra using the least-square method

Akaoka, Katsuaki; Oba, Masaki; Miyabe, Masabumi; Wakaida, Ikuo

no journal, , 

For quantitative analysis of the fuel debris using Laser Induced Breakdown Spectroscopy (LIBS), great deal of analysis and identification of spectra are necessary. Therefore, we tried "the analysis of the LIBS spectrum by the least-squares method" as quantitative analysis without identification and analysis of the spectra. As a result, the calibration curves for quantitative analysis could be got without them.

Oral presentation

Development of quick and remote analysis for severe accident reactor, 2-4; Estimation of LIBS spectra using the least-square method

Akaoka, Katsuaki; Oba, Masaki; Miyabe, Masabumi; Wakaida, Ikuo

no journal, , 

For quantitative analysis of the fuel debris using Laser Induced Breakdown Spectroscopy (LIBS), the measurement of the spectrum data for combination of materials is necessary. Therefore, we tried the estimate of the unknown elemental combination mixture spectrum, using "the analysis of the LIBS spectrum by the least-squares method". As a result, estimated spectra accorded with an actual spectra well.

Oral presentation

Development of quick and remote analysis for severe accident reactor, 6-2; Analysis of LIBS spectra using the least-square method for simulated fuel debris

Akaoka, Katsuaki; Oba, Hironori; Wakaida, Ikuo; Ouchi, Atsushi*; Mizusako, Fumiki*; Eto, Yoshinori*; Torimaru, Tadahiko*

no journal, , 

For measurement of the fuel debris from the Fukushima Daiichi Nuclear Power Station accident, we analyzed the LIBS spectrum of the mixed simulated fuel debris of U, Zr and Fe, using the least-squares method. We present the results of the calibration curve and analysis spectrum.

Oral presentation

Analysis of the two-dimensional composition distribution measured by LIBS using the least-squares method

Akaoka, Katsuaki; Ogawa, Chihiro*; Tagawa, Akihiro; Wakaida, Ikuo

no journal, , 

The two dimensional distribution measurement is possible using the laser induced breakdown spectroscopy. We analysed the two-dimensional composition distribution measured by LIBS using the least-squares method. As the result, distribution of the contribution ratios of a sample provided using the least-squares method expressed element distribution of the samples well.

Oral presentation

Analysis using the least-squares method of two-dimensional distribution of the simulated fuel debris measured by the LIBS

Akaoka, Katsuaki; Ogawa, Chihiro*; Tagawa, Akihiro; Wakaida, Ikuo

no journal, , 

The two dimensional distribution measurement is possible using the laser induced breakdown spectroscopy. We analysed the two-dimensional composition distribution of the simulated fuel debris measured by LIBS using the least-squares method. As the result, distribution of the contribution ratios of the simulated fuel debris provided using the least-squares method expressed element distribution of them well.

Oral presentation

Development of a robust nuclear data adjustment method to outliers

Fukui, Yuhei*; Endo, Tomohiro*; Yamamoto, Akio*; Maruyama, Shuhei

no journal, , 

no abstracts in English

Oral presentation

Investigating cross-section estimation results with Gaussian process regression; A Comparison with GLS results for $$^{235}$$U(n,f) cross section

Iwamoto, Hiroki

no journal, , 

In the evaluation of nuclear data, in energy regions where cross sections are difficult to predict with physical models, the evaluation is based on experimental data. A regression method called generalised least squares (GLS) is used in this evaluation, but recently another method called Gaussian process regression (GPR) has attracted attention in the field of machine learning. In this study, using the neutron-induced fission reaction cross section of $$^{235}$$U as an example, the cross section and its uncertainty (covariance, correlation coefficient and standard deviation) were evaluated using GPR and compared with the results of the GLS evaluation. The comparison showed that the two methods differ in the evaluation of correlation coefficients and standard deviations, but generally show similar trends.

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