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Kanzaki, Norie
Hoshasen Seibutsu Kenkyu, 56(3), p.295 - 307, 2021/09
The biological effects of low-dose radiation are confusing due to the various intertwined factors. The vital body responses are complex. In this review, we visualized the results of animal experiments using Self-organizing maps (SOM) and reported the results of the low-dose radiation biological effect assessment from a different viewpoint. For example, although the classification of these data which were the biological effects by low-dose radiation were impossible, SOM got the overall assessment and the intuitive understanding. We reported the results and the usefulness of data visualization of radiation biological effects using machine learning.
Nakajima, Norihiro
Nihon Genshiryoku Gakkai-Shi ATOMO
, 59(8), p.34 - 38, 2017/08
It is necessary the reading comprehension of output data to utilize the simulation in a design process, besides of the input data preparation. The simulation introduces enormous big data for evaluation. This paper describes data analysis technology in the analysis and the evaluation process of the output. The technology applies the artificial intelligence to minimize the unpredictable issues and oversight. It is based on the artifact engineering, which is a multi-sight abduction methodology, which derives a hypothesis.
Nakatani, Takeshi; Inamura, Yasuhiro
Hamon, 26(1), p.42 - 45, 2016/02
In the Materials and Life science experimental Facility (MLF) of J-PARC, the computing environment group was organized from the construction of MLF. The group has been developed and operated the neutron event-recording data acquisition (DAQ) system, the data analysis library and the device control software framework for neutron experimental instruments in MLF. In this article, we report the new developments as follows: The universal event-recording DAQ system to make the most of the intense neutrons; the data process framework to enable multi-dimensional data analysis at various neutron instruments; the remote access to be easily able to monitor a measurement status and handle many kinds of enormous data from anytime, anywhere.
Matsuda, Toshiaki; Totsuka, Toshiyuki; Tsugita, Tomonori; Oshima, Takayuki; Sakata, Shinya; Sato, Minoru; Iwasaki, Keita*
Fusion Science and Technology (JT-60 Special Issue), 42(2-3), p.512 - 520, 2002/09
Times Cited Count：3 Percentile：23.39(Nuclear Science & Technology)no abstracts in English
*; *; Yabuuchi, Satoshi
JNC TY7400 2000-001, 72 Pages, 2000/03
JNC-TY7400-2000-001.pdf:4.01MB
None
Ikeda, Takao*; Yoshida, Hideji*
JNC TJ7400 2000-006, 159 Pages, 2000/02
JNC-TJ7400-2000-006.pdf:4.81MB
no abstracts in English
Kurihara, Kenichi
Purazuma, Kaku Yugo Gakkai-Shi, 76(1), p.65 - 82, 2000/01
no abstracts in English
Hunter
PNC TN9410 98-015, 81 Pages, 1998/02
The study was carried out within the framework of the PNC-CEA collaboration agreement. Data were provided, by CEA, for an experimental loading of a start-up core in Super-Phenix. This data was used at PNC to produce core flux snapshot calculations. CEA undertook a comparison of the PNC results with the equivalent calculations carried out by CEA, and also with experimental measurements from SPX. The resu1ts revealed a systematic radial flux tilt between the calculations and the reactor measurements, with the PNC tilts only 
30-401 of those from CEA. CEA carried out an analysis of the component causes of the radial tilt. It was concluded that a major cause of radia1 tilt differences between the PNC and CEA calculations lay in the nuclear datasets used: JENDL-3.2 and CARNAVAL IV. For the final stage of the study, PNC undertook a sensitivity analysis, to examine the detailed differences between the two sets of nuclear data. The PNC flux calculations modelled SPX in both 2D (RZ) and 3D (hex-Z) geometries, using the diffusion programs CITATION and MOSES. The sensitivity analysis of the differences between the JENDL-3.2 and CARNAVAL IV nuclear datasets used the SAGEP calculational route. Both datasets were condensed to a single, non-standard, set of energy group boundaries. There were some incompatibilities in the cross-section formats of the two datasets. The sensitivity analysis showed that a relatively small number of nuclear data items contributed the bulk of the radial tilt difference between calculations with JENDL-3.2 and with CARNAVAL IV. A direct comparison between JENDL-3.2 and CARNAVAL IV data revealed the following. The Nu values showed little difference (<5|%). The only large fission cross-section differences were at low energy (<30% otherwise, with <10% typical). Although down-scattering reactions showed some large fractional differences, absolute differences were negligible compared with in-group scattering; for in-group scattering fractional ...
; ;
PNC TN9410 97-087, 142 Pages, 1997/07
Computer data analysis is planned as an essential process to facilitate and speed up the ISI of MONJU steam generator tubes using the ECT technique. This process compares the phase and amplitude of the signal in a vector window in order to identify and categories defects. The categorization of the inspection signal requires a high level of precision. The analysis test was carried out taking the best operational conditions for reference. From this, the most accurate classification conditions were established. The MONJU PSI signal data was used to check the effectiveness of the process. The results are as follows. (A) Verification of the set parameter for off line processing. Automatic classification is possible for almost all the support plate signals. Classification of all the weld and bend signals was not possible. Therefore, the set parameter was selected for the category in which there were the largest number of signals was established. (B) Verification of the analysis processing conditions. The established analysis conditions allow automatic classification for about 80 to 85% of the signal comparison factor cases. Furthermore, it is possible to classify all the signals by additional operator intervention. In this way it is possible to analysis and evaluate all the MONJU steam generator tube ISI data. (C) Improvement of the data base. Evaluation of MONJU PSI flaw detection data was carried out by set parameter analysis. FOllowing these results the necessary data base for ISI signal evaluation was created.
Ohara, Kinichi*
PNC TJ1676 97-001, 221 Pages, 1997/03
None
Yanagisawa, Hiroshi; Mineo, Hideaki; Dojiri, Shigeru; Takeshita, Isao
Dai-16-Kai Kaku Busshitsu Kanri Gakkai Nihon Shibu Nenji Taikai Rombunshu, 0, p.117 - 124, 1996/00
no abstracts in English
Yanagisawa, Hiroshi
JAERI-Data/Code 95-007, 90 Pages, 1995/05
JAERI-Data-Code-95-007.pdf:4.27MB
no abstracts in English
Yanagisawa, Hiroshi
JAERI-Data/Code 94-008, 59 Pages, 1994/08
JAERI-Data-Code-94-008.pdf:1.49MB
no abstracts in English
Yanagisawa, Hiroshi
JAERI-Tech 94-005, 184 Pages, 1994/07
no abstracts in English
*
PNC TN9410 92-278, 347 Pages, 1992/09
A series of critical experiments for conventional two-zone homogeneous cores of 6 to 8 MWe-class LMFBR, JUPITER phase-I, were analyzed and evaluated using the latest analytical method, which had been established from the preceding numerous studies on fast reactor physics. The present work is a part of efforts to develop a standard data base for LMFBR core nuclear design at PNC. The analytical method and results are summarized as follows: (1)Analytical method (a)Nuclear data : 70-group fast reactor constant set JFS-3-J2(1989 edition) based on the Japanese Evaluated Nudear Data Library, version 2 (JENDL-2). (b)Cell calculation : plate stretch model, cell heterogeneity treatment by Tone's method and transport cross-sections weighted with neutron current. (c)Base core calculation : 18-group, three-dimensiona1 XYZ diffusion theory and Benoist's anisotropic diffusion coefficients. (d)Correction calculation : three-dimensional transport effect, mesh size effect, cell asymmetric effect and all master model effect etc. (2)Analytical results (a)The C.E (calculation/experiment) values of criticality agree quite well among seven cores (ZPPR-910D/2) and do not depend on the core volume or the number of control rod positions (CRP). (b)The C/E values of control rod worths increase gradually from the core center to the core edge positions in each core (511%). Those of reaction rate distributions also indicate similar spatial variations (25%), which is considered to be consistent with the C/E tendency of control rod worths. (c)The reaction rate ratios of C28/F49 and F25/49 give quite stable C/E values of 1.06 and 1.03, respectively. (d)The C/E values of sodium void reactivities are overestimated by +25% at core center region. The C/E dependence on void region size, which was pointed out in the past analyses, is found in the ZPPR-9 core, but not in the ZPPR-10 series. (e)The C/E dependence of 4% on the radial positions were found in sample ...
